ML19350D374

Sar:Tech/Ops Model 770 Type B(U) Package

ML19350D374
Person / Time
Site:	07109148
Issue date:	03/20/1981
From:	TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML19350D373	List: ML19350D372 ML19350D374
References
18818, NUDOCS 8104150343
Download: ML19350D374 (50)

Text

l i

Tech / Ops

/

1 Pa6at: Ort Products %w M North Avenue 0""'"70n. Massachusetts 01803 I Phone (617) 272 2000 SAFETY ANALYSIS REPORT TECH /0PS MODEL 770 TYPE B(U) PACKAGE

1.

General Information 1.1 Introduction Tech / Ops Model 770 is designed for use as a source changer, storage container, and Type B shipping container for radiographic sources in 60 special form. The capacity of the container is 550 curies of cobalt The container will accept Tech / Ops sources listed in Section 1.3.

These sources have satisfied the requirements for special form radioactive material and have been issued IAEA Certificate of Competent Authority Nu=ber USA /0165/S. A copy of this certificate is included in Section 1.3.

The Model 770 is similar in design and construction to the Model 771 source changer-shipping container. The Model 771 has been previously approved as a Type B shipping container and has been issued USNRC Certificate of Compliance Number USA /9107/B and IAEA Certificate of Competent Authority Nu=ber USA /9107/B. A copy of these certificates are contained in Section 1.3.

1.2 Package Description 1.2.1 Packaging The Tech / Ops Model 770 Source Changer measures 23 inches (58cm) long, 24 inches (61cm) wide and 20 inches (51cm) high. The gross weight of the container is 813 pounds.

The radioactive source assembly is housed in a zircalloy or titanium "S" tube. The "S" tube has an outside diameter of.563 inch (14.3mm) and a vall thickness of 0.035 inch (0.89mm). Prior to bending the source tube into the "S" form, a titanium of zircalloy source stop is poritioned at the center of the tube. The tube is rolled to secure the source stop in position. The source tube is then bent to the "S" form.

The radioactive source asseibly is installed in the shippir.g container such that the radioactive source capsule contacts the source stop in the "S" tube. The source is held in position by means of the lock assembly.

The lock assembly secures the source assembly by firmly engaging the teleflex wire of the source assembly. To locking pins with forked tines engage the teleflex wire between the spiral wrap. The selector ring is secured-ir. the locked position by a plunger style key operated lock, Corbin Na. 02291I., which is mounted in a lock holder. When the lock is depressed and engaged, a pin, which is an integral part of the plunger, engages a drilled hole in the selector ring and prevents its rotation from the locked position. The lock assemblies are mounted on the end plates of the inner container by 5/16 - 18 UNC hex head bolts. The bolts are lockwired in pairs to prevent inadvertent loosening or removal. The

,~*

1sek assembly is protected from damage during an accident by the 8 inch x 10 inch rectangular tubing welded between the inner and outer containers, by the outer container itself, and by a 0.25 inch (6.4mn) thick cover Revision 0 20 March 1981 1-1

two lock assemblies and secured to the container with eight 3/8 - 16 UNC bolts. These bolts are seal wired in groups of three on each end of the cover plate. This provides assurance that the cover plate does not detach during transport, and provides a tamper proof seal.

1.2.3 Contents of Packaging 60 The Model 770 is designed for the transport of cobalt in quantities up to 550 curies as Tech / Ops source assemblies listed in Section 1.3.

These capsules satisfy the requirements for special form radioactive materials in accordance with 10CFR71 and IAEA Safety Series No. 6,1973 Edition.

Revision 0 20 March 1981 1-4

= _ _ _ _.

1.3 Appendix i

1.3.1 Table of Source Model Numbers 1.3.2 Certificate of Competent Authority USA /0165/S 1.3.3 Certificate of Compliance USA /9107/B 1.3.4 Certificate of Competent Authority USA /9107/B 1.3.5 Descriptive Assembly Drawings i.

1

\\

l l

i Revision 0 f

20 March 1981 I

I 1-5 L

t 1.3.1 SOURCE ASSEMBLIES COMPATIBLE FOR USE WITH HODEL 770 SHIPPING CONTAINER Assembly Model Number Capsule Number A-4 24-3 60001 or 60011 A-424-4 60000 or 60011 A-4 24-7 60002 or 60012 A-424-8 60000 or 60011 A-424-13 60002 or 60012 A-424-16 60000 or 60011 A-424-17 60000 or 60011 A-453-1 60000 or 60011 A-453-2 60002 or 60012 A-453-5 60007 or 60012 A-453-7 60000 or 60011 A-453-8 60000 or 60011 A-453-9 60000 or 60011 A-453-10 60000 or 60011 Revision 0 20 March 1981 f

1-6 e

-.*e--

m 4-.

e

+.

~w-n w-,

,v

~

O e

Certificate Number USA /0165/S, Revision 0 Page 2 y

4 II.

This certificate, unless renewed, expires on September 30, 1982.

This certificate is issued in accordance with paragraph 803 of the IAEA Regulations and in response to the July 26, 1979, petition by Technical Optv.ations, Inc., Burlington, Massachusetts, and in consideration of the associated information therein.

Certified by:

l 1

M /Z/979 l

6/

(Date)

R. R. Rawl Designated U.S. Competent Authority for the International Transportation of Radioactive Materials Office of Hazardous Materials Regulation Materials Transportation Bureau U.S. Department of Transportation

,~

1" Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition" published by the International Atomic Energy Agency (IAEA), Vienna, Austria.

Title 49, Code of Federal Regulations, Part 170-178, USA.

' ~~

2 REE3 ION O

~ M 2 o sir 8 i-a

i

\\

F cam N A C 418 U.S. NUCLE AR f EGULAToRY COMMISSION

.,[gpq CERTIFICATE OF COMPUANCE 2 73)

. For Radioacsive Meterials P*'**T" 1.fel Certificate Nuweer 1.ibt Revision No.

1.(c) Package identification No.

1.(d) Pages No. 1.(e) Tot al No. Pages 4107 n

IKA/01n7/Rf) 1 9

2. PRE AMBLE 2.le)

This certificate is issued to satisfy Sections 173.393a.173.394,173.395. and 173.596of the Department of Transpo..non Hazardw Materials Regulations (49 CFR 170189 and 14 CFR 103) and Sections 146-19-10e and 146-10-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amerused.

6 7.lb)

The packaging and contents described in item 5 below. meets the safety standards set forth in Subpert C of Title 10. Code of Federal Regulations. Part 71. ** Packaging of Radioactive Materials for Trars, ort eM Transportation of Radioutive Material Urder Cer1ain Conditaons.**

2.fcJ This certificate does not relieve the consignor from compliance with any requirement of ttie esguistions of the U.S. Department of Trarvsportation or other applicable reguietory agencies, including the government of any country through or into which the package well be transported.

3. This certificate is issued on the basis of a safety analysis report of the package design or application-3.fa)

Prepared by (Name and address):

3.(b)

Title and identification of report or asplication:

J Technical Operations, Inc.

Technical Operations, Inc. application dated Northwest Industrial Park December 27, 1977.

e Burlington, Massachusetts 01803

3. lei Docket No. 71-9107 4 CON D'I TIONS This ca.tificate is conditional upon the fulfilfing of the requirements of Subpart D of 10 CFR 71, as applicable. and the conditions specified in item 5 telow.

5. Description of Pacoging and Authorised Contents. Model Nurrcer, Fissile Cass. Other Conditions, and

References:

(a) Pacitaging (1) Model No.: 771 (2) Description N

The Model No. 771 shipping container is designed for use as a

.f source changer, storage container and Type B Shipping Container for radiographic sources in special fonn. The capacity of the container is 110 curies of cobalt-60 as special form._ The container will accept certain Tech / Ops wire mounted radiographic sources which have been deemed to neet the requirements of special l

form. The Model 771 Source Changer easures 23 inches.longo 24 inches wide and 20 inches high. The radioactive source assembly is housed in a Zircalloy "S" tube. The Zima11oy tube is surrounded by depleted uranium metal as shielding material. The depleted uranium shield assembly is eaCased in a steel housing.

The void space between the depleted uranium shield assembly and

^

the inner container.is filled with a rigid polyurethans fam.

The gross weight of the container is 690 pounds.

i ILNSION o MAR.2 0 4WI

Page 2 - Certificate No. 9107 - Revision No. 0 - Docket No. 71-9107 (3)

Drawings The packaging is constructed in accordance with Technical Operations, Inc.. Drawings Nos. 77103, Sheet 1 and 2 of 2 Rev. A.

(b) Contents (1) Type and form of material Cobalt-60 as sealed sources that meet the requirements of special form as defined in 571.4(o) of 10 CFR Part 71.

(2) Maximum quantity of material per package 4

110 curies 6.

Source assemblies for use in this packaging are limited to those assemblies as identified in Appendix A to Technical Operations, Inc. application dated December 27, 1977.

7.

Nameplates shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.

B.

The packaging authorized by this certificate is hereby approved for use under the general license provisions of Paragraph 71.12(b) of 10 CFR Part 71.

9.

Expiration date:

February 28, 1983.

REFERENCES Technical Operations, Inc. application dated December 27, 1977.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

~

i Ik Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety MAR 3 1 Egg Date:

REVISION O

.n 2 o nsu

,.,o

.,.-w--.

m y

,,.._,_.m..c, m

y,%

ca,..

3 DEPARTMENT OF TRANSPORTATION MATERIALS TRANSPORTATICN BUREAU

.r' wAssisotou, or 2o59o IAEA CERTIFICATE OF COMPETENT AUTHORITY Type B Radioactive Material Packsge Design Certificate Number USA /9107/B ()

This establishes that the packaging design described herein, has when loaded with the authorized radiocctive contents, been certified as meeting the regulatory requirements for Type B packaging for radioactive materials as prescribed in IAEA1 Regulations and SS 49 CFR 173.393b and 173.395 (b) (2)

Regulations for the transport of radioactive 2

of the USA materials.

I.

Package Identification - Tech / Ops Model 771.

Package Description - Packaging authorized by this II.

certificate consists of a Zircalloy "S" tube supported by rigid 2

polyurethane foam, surrounded by depleted uranium shielding and iscased in steel housing measuring 23" long by 20" high.

Gross weight of the package is 690 pounds.

Authorized Radioactive Contents - The authorized contents III.

consist of Cobalt-60 sealed sources meeting the requirements for special form (49 CFR 173.398(a)) with a maximum activity of 110 curies.

IV.

General Conditions -

Each user of this certificate must have in his a.possession a copy of this certificate.

Each user of this certificate, other than Tech / Ops b.Burlington, MA shall register his identity in writing to the Office of Hazardous Materials U.

S.

Operations, Materials Transportation Bureau, D.

C.

Department of Transportation, Washington, Washington, D. C.

20590.

This certificate does not relieve any consignor c.or carrier from compliance with any requirement of the Government of any country through or into which the the package is to be transported.

Marking and Labeling - The package must also bear the V.

as well as the other marking and labels marking USA /9107/B()

prescribed by the USA Regulations.

BEVISION O

• MAR.2 0 691

..,e

o Certificate Number USA /9107/3 ()

Page 2 VI.

Expiration Date - This certificate, unless renewed, expires on April 30, 1981.

This certificate is issued in accordance with the requirements of the IAEA and USA Regulations and in response to the April 4, 1978 petition by Tech / Ops, Burlington, MA and in consideration of the assoicated information provided in USNRC Certificate of Compliance No. 9107 (Appendix A).

Certified by:

kk I9, /f 7f A. W. Grella (DATE)

Chief, Technology Division Office of Hazardous Materials Operations Materials Transportation Bureau Washington, D. C.

20590 1" Safety Series No.

6, Regulations for the Safe Transport of Radioactive Materials, 1967 Edition" published by the International Atomic Energy Agency (IAEA), Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, USA.

I i

i 4

i i

REVISION O

. MAR.2 0 89 E t

.,z i

e 12 3

o$

8 Ea @1sn

~@ss !a l l Ua 2

E b

• g i,

E se s

s Eeb o

g

@s s

Bbi m

g WF

• i e

E d%

v

&N *{

Sh 5

j E

es s

Es g

{d s a

s8

=

a

.e oE' m

g

,o gmL

.g)g o c.

en

-~

m i

9 E

a

}M3!! i.

E$

5 i-

?eg5e c1 N

N N

'x \\

_xm\\

s 40-,j s s

~

e

./

s

n..i m m w c

E k

si

\\

s

! l l$ 1

/

x-

/

b

+

4 1

x l

/

I

\\ g

// j i.

\\

\\

lp jdj

\\

5

.i/

/ft

,o n

ce W

E

\\

8 E2 6E

\\/

/

eE s

1,/

-in o

kR c<

A 6

O P-

,- o

E 3

e U

I a

Fe_

• a

!! $p 9

E t

2 ils g"h'8 ;

s sed We is 9

5$$

20 3-2 l

g

.j MX y sf

,5

's eEi oge i

zag a

==

g

!h I$

'la3 te i

1

.;g

'E w

i]i N

11 a

g

!!;.i

,;1 s

( bl$

n I.

i.

\\\\

k g

\\

s

\\

/

/

\\

,x x

/

\\

\\

E

\\

/

e f

//

//

\\/

s9 5 E O 2

/

v/

/t_v/

c b ~g

/

x s:

/

9 5 El N Y

=$

z 5 E

L 0

Eg

~

M l

8 0

I E

i-s

Tr090l l-' l -" l y

o u

11 LOCK ASSEMBLY (2) ll l'

(SEE FULISi2E VIEWS-SF* 5) p is il s'

lI 11 il 11 I

i

.I l

l liiNER CONTA1HER END PtATE (2) i (WEtDED AFTER tr15TAtut6 91lELD) l I

n METM-FIMM (SEE DOTE BELOW) w:

r,x

.x x x x

x x

x N /

/

/ '

/ /,g/

/

// '/

r*

-SOURCE STOP

),\\

/

/

(ZlRCALLO( OR TITANIUW I

A

's ',

l w

/ p'

', 's

"[

l' 00URit6 HOLE - INNER CONTAlf1ER s

N i

FILLED WITH METR-FDW LEH-M

/'

\\

(RIGID POLYURETIMNE FDAM) s, '{ _ '

s

\\

h'

\\ 's j' N_

/

i MIN.CLEN%NCE g

g_

(DEPLETED URAfiUM) SEE SHT 6

/ /

/ -

/ /

$O0KE TUDE(ZIRCALL0f 0R TITINN)

/

,,t 9/l6 QQ s.0W WALL CAST INTO SHIELD C i y (TYP l

I 4

l i

!l l

1 g

fl ilI

!I I,

'I ll

-RADIOACTNE 5OURCE I

I l

ll fI (IN '3TORED POSITION) ii ll l:

II II

'i

~"~" A5 norED

"*EIh55 SECTION A-A W5beo70 Souace omnGER

'~

~

g7f~~ =.,.ri s.

CEScRIPDVE ASSEMBLY 2:

,I- ~"'ifI"77090 ld

~.

.~

..., a i s., m

~

8 R

l

)(4 E

Gy L

t e

D E

1 d* We H

E M

T 1

~

1 (4

E E

OE

)

L 9

5 E S 0,.

E D

K T

E C S 9,_

4

)

)S 1

L T

4 (4 D O

RA 0,

)

L (4 )L W

OI E

Rt P

E*

(

7 f

U E 7

L E

O GA R

O.

V i

Am D

V NW C

SI 0 P f~

S M

E B

)8 O L

T B0 I

E D

GL

( C 8

G H

L 7

I

)

St UJ N

t NO P

T 's C$

7 R Ta T

R RA I

C Y

I N

T Ax L Si EI U

t EW I

l

(

E E

LS 5

P A

D E S3 A

C f

y C/

]OD' m

=

~

t P0 T

L4 E=

N O3 Ed T

a C G.

R/

f M

(

Nl Ng4 N

)0 7 /

M o

U l

1._.

s l

D O

E

=

(

R N%

O N

~

T A

5

+

R A

a Q(

=

K

=

I E

S R

g E

p P

c PO x

i-M f

1 C

- I s

.N

\\

I g

x M

3g

.q,,

x Q

p 1

)

E 2

TA B

• r L

l I

P B

EE G )L s

i W s nE j

LE E

M ET i

o VS v

)

E(

R R

[

M L

F I

(

N" d

M 1

)4 f

E,

(

5

_~g B

/

)

C S

~

B S

L 0

G 7

N 3

U )L SE M

Y t E

=

LU J

T D

D Bi l

)

A (S 4

n MtA

( )L E

E R TE S

R S U UE T AD NS E

1 D

r E

m)

T GD L

E T F E E NL L

I L

oE IHP TO r

SR C (R SE U

C D

RE J

L l

ET DO

(

0 N A A (C 9

L N

7 I P 0

7

~ ;

N "6' Y L

)

^B

)

(4 M

2 4

w E

(

W e

d

~

S

'S 0,

E a

(

'a A 9_

R c

A C

D

"^

E oE 7,

5 0

S

) )D D

2( C H

2 oV D

R D

7 H

n T

=i 'P iL oI T

PL

'7 R A

RI r

N i

C G D g

R )L 0

'S

~

L F) n E

E L

iL 4,-

m(T n pB e

2 E Kt e

oD E

g 3 E C

t T

O S

i 5

0 S Lb g

7-(

1 (

Nt i T

" /

/

)

)

L

'T eE oE 3

y s$

F a(Y r

g g.

O 1

e

[gp/~

/

7 T '. 7/

's 5

M w~

S.

u e9 e

(4 A 9

m~

yx L

A -

g7

~

s wA I

~

s eN gs u

A sF

=

c T

l r

x D

)

3 r -

x A

Q-D 2

r nE

(

u xR W

eW E

)L 4,

R E

C E

e,yD i

S GT nS

.e, H

RD f

E o

s D

RL M

)

i E

L l

DO x

Bg lC R 2

2e ED

(

e 1e L

G

)L n

L T

E O

o 0 S SC sE#

N)

)

I t

L

• J(

)L RS e

E

(

E PR Ym E

E SI o

T W

om S

T R S 1

D E

0 C s

E Dm 1

S T E n

0I km AL e

L L i 5U Of_

5 HO EM cF LO s

R R

oD PR o

L L

c K

P E X

KD CD ME O

CL L

O O OT

(

OO LC C (5 LC

%@ N Q

O

(

(

7 N

xON D

~

E g

.,9 di K

O-O C

\\y

\\

f O

)

s L

9^N qN hF[

s" O

6 D

c N%

i1 i E

O O

K y- -

L v

CO

~

Ns sO

~

N l i U

s

)[

C O

o 1090 7

7

<o R

l E

5 G-k YL 6

WB m

M

~

T CE I

ES 0

C S 9,.

R A 0

G E

U 7i E

O V

7 Si l

0 PR-I 77 I

LSCU C a~ m i

E E-l MmD 1

.O r

M w-s i

)

. 3 t-0

=

ct lll y,

/

1 r

w ~r.=

nc r

r

g

=

j A

5g T

3 M

5 C

8 1

L D

L 0

E 7

IH 3

S s

iO

/

4 561 0

/

l

/

Y i

D 109o 7

7 r,

i

2.

Structural Evaluation 2.1 Structural Design 2.1.1 Discussion The Model 770 consists of six structural components: source capsule, shield assembly, shield retaining assembly, inner container, outer container, and locking assembly. The source capsule is the primary containment vessel. It satisfies the criteria for special form radio-active material. The shield assembly fu11 fills two functions. It provides shielding for the radioactive material and, together with the locking assembly, assures proper positioning of the source and provides a positive closure. The shield retaining assembly consists of four retaining bars mounted on eight adjusting screws and nuts that are welded to the inner container. The assembly ensures proper positioning of the shield and gives the package added structural integrity. The inner and outer containers provide the structural strength of the package.

The inner container is attached to the outer container with fout 3" x 1%" x.18" wall thickness steel tubing and with two end plates. The tubing and end plates give added strength to the package.

2.1.2 Design Criteria The Model 770 is designed to comply with the requirments of 10CFR71 and IAEA Safety Series No. 6,1973 Revised Edition for Type B (U) packaging.

2.2 Weights and Centers of Gravity The Model 770 weighs 813 pounds (370kg). The shield assembly contains 370 pounds (168kg) of depleted uranium. The center of gravity is the center of the uranium shield. It is located axially, 11 inches (279 mm) from the bottom.

2.3 Mechanical Properties of Materials The inner and outer containers are made out of hot rolled steel which has a yield strength of over 40,000 psi and a tensile strength in excess of 40,000 psi. The source capsules, and all bolts are made out of type 304 or 304L stainless steel, which also have a yield strength of over 40,000 psi.

The capsules are sealed by tungsten inert gas welding. Drawings of the capsules are enclosed in Section 2.10.

~

2.4 General Standards for All Packages 2.4.1 Chemical and Galvanic Reactions i

The materials used in the construction of the Model 770 are uranium metal, stainless steel, carbon steel, zirconium, titanium and copper. There will be no chemical or galvanic action between any of these components. There is no Revision 0 20 March 1981 2-1 i

iron-uranium interf ace in this package. Therefore, there is no possibility of the formation of an iron-uranium eutectic alloy at elevated temperatures.

f S.2 Positive Closure

.4 The source assembly in the Model 770 cannot be exposed without opening a

.h key operated lock. Also, end plates are secured to the outer container with eight seal wired hex head bolts to prevent access to the package contents. Thus positive closure is provided.

6.3 Lif ting Devices

ial te Tha Model 770 shipping container is designed to be handled in two ways.

.s Three lengths of square tubing are welded to th9 bottom of the outer arm container base plate. These lengths of tubing act as skids to f acilitate i

tha use of a fork lift in handling the shippi*d container. In addition, two eye bolts are attached to the top of the contr!aer. These shouldered cymbolts, Armstrong No. 27, 5/8-11 UNC x 1-3/4" long, are threaded into tha tapped square bars under the outer container top plate. The shoulder is then welded to the container top plate. The load required to break ona 5/8-UNC thread is calculated to 13,500 pounds. The manufacturers a

breaking strain is given as 16,000 pounds. Both of these values are ovsr 16 times the weight of the package. Therefore, the lifting system is capable of supporting more than three times the weight of the package ca prescribed in 10CFR71.31 (c).

4.4 Tio Down Devices Tha eyebolts can be used as tie down devices. The shear strength for steel is approximately 0.75 times the tensile strength (reference:

Machinery's Handbook, 20th Edition, P452), and is approximately 10,000lbs.

This is over 12 times the package weight. Therefore the eyebolts comply with tha requirements of 10CFR71.31 (d).

,5 Standards for Type B and Large Quantity Packaging nn

.5.1 Load Resistance Tha package is considered as a simple bean with the outer container the sole structural member, and supported on both ends. If a uniform load of five times the package weight is evenly distributed along its length, thm maximum stress generated can be computed from:

1 is c: )),

8Z Where: a: maximum stress generated F: total load (4065 pounds) lengthofbeam(24 inches})

L:

section modulus (146.42in Z:

id Revision 0 20 March 1981 2-2

To demonstrate that the radioactive source assemblies will remain in their shielded pcsition following the hypothetical thermal accident, the follow-ing analysis is presented. At the conclusion of the thermal test, it ik assumed that the polyurethane foam has completely escaped from the package.

The shield assembly is prohibited from moving by the retaining bar assembly and leveling plate. Thus, it is concluded that the Model 770 satisf actor-ily meets the requirements for the hypothetical accident - thermal condition of 10CFR71.

2.7.4 Water Immersion Not Applicable 2.7.5 Summary of Damage The test designed to represent the hypothetical accident conditions caused minor deformation but 'no reduction of shielding effectiveness nor loss of structural integrity.

2.8 Special Form The Model 770 is designed for use with Tech / Ops source assemblies which are listed in Section 1.3.1 along with the corresponding source capsules. These capsules have been tested to the criteria for special form radioactive material in accordance with the requirements of 10CFR71 and IAEA Safety Series No. 6,1973 Edition with satisfactory results. They have been issued IAEA Certificate of Competent Authority USA /0165/S.

2.9 Fuel Rods Not Applicable Revision 0 20 March 1981 2-6

-~. -

I i.

2.10 Appendix 1

i Model 770 Drop and Puncture Tests l

Model 770 Penetration Test Descriptive Assembly Drawings - Source Assemblies I

i f

l i

1 I

t l

}

l 1

1 i

i t

t i

l r

1 l

Revision 0 20 March 198.

i l

l 2-7

TEST REPORT RADIATION PRODUCTS DIVISION

SUBJECT:

Model 770 Drop and Puncture Test By:

Keith Spinney Date:

16 January I?81 On 16 January 1981, a drop test and puncture test were performed on a Model 770 source changer, Serial Number 1.

The Model 770 was raised 30 feet (9.1m) by crane and dropped twice on to a frozen packed gravel surf ace covered by a 4 ' x 4' x %" thick and a 3' x 3' x 3/8" thick steel plate.

The first drop, the Model 770 impacted the ground in an upright horizontal position and suf fered no adverse affects. The second drop, the Model 770 impacted at a sligM: angle, and as a result the ends of the three skids were deformed slightly. The Model 770 sustained no loss of structural integrity.

The same Model 770 was then subjected to a free fall of 40 inches (Im) onto a steel billet measuring 8 inches (203mm) hign by 6 inches (L52mm) diameter which was positioned on the two steel plates described above. The Model 770 impacted each time on a cover plate, which was deemed to be the most vulnerable surface. Each cover place suffered only minor deformation. One of the bolts securing a cover plate to the Model 770 suf fered damage.

Upon completion of the tests, the cover plates were removed. The lock mech-anisms were determined to have suffered no damage, and the two dummy sources weresgfilinplace. The Model 770 was then loaded with 391 curies of Cobalt and a radiation profile was taken. There was no change from the radiation profile taken before the test.

Therefore, it is concluded that the Model 770 satisfies the requirements for the drop test and puncture test, as described in 10CFR71 Appendix A and 1AEA Safety Series No. 6, 1973 Edition.

tchti J O Witnessed:

Francis E.

y REVISION O MAR. 2 O r988 2-e

w-._-ww

--naw g---

ana- -,, - -

-,_a.a ma.

-- - -+a

_w s,_.<__a

__m,,__,,x,_

___2_..am__wa

-a,-

1-_,aa_a,,,,,--ea_

m__

,s h

e e

e e

Ae Mem

^

wm emeeen mo i

l

. e l

~

I L

I

~

=

/ /

p

#3ea,

l l

P00R BRIGIN4

~

i m~

REVISION O I

MAR. 2 0 1985 2-9

c t

ss j., -

I 2-..

l v

l

-YS

~

• ^~s&g r4

..7-

':.*..*~~

l'.

i st?:.}i'L

~

i

,i P00R BRIGlmi i

l l

~

.m. -

5 O

.. '.8 y}

+

e

_t

.h t

_. ~

REVISION O MAR.2 0 #9st z-no

TEST REPORT RADIATION PRODUCTS DIVISION

SUBJECT:

Model 770 Penetration Test BY:

Francis E. Roy, Jr.

DATE:

23 March 1981 On this date a penetration test was performed on a Model 770 source changer, serial number 1.

A steel cylinder,1.25 inches (32mm) diameter and 13 pounds (6kg) in weight, was dropped from a height of 40 inches (1 meter) onto a cover plate, the most vulnerable part of the container. Upon completion of the test the cover plate was examined fcc damage. Only minor deformation was observed as a result of the impact. The structural integrity of the cover plate and the Model 770 was sustained.

As a result of the penetration test there was no loss of structural integ-rity nor loss of shielding effectiveness.

Therefore, it is concluded that the Model 770 source changer satisfies the requirements for the penetration test as described in 10CFR Part 71 Appendix i

A and IAEA Safety Serial No. 6 1973 Edition.

o a

Witnessed By:.

/ i' FER/js REVISION O lh. 2, s t ri

i t

,i

l l

t t

' i

.I l

i i

i i

f 1..

W '

t.. _

l

$ " bj'. 99. +_$$ll5~gaf Af

/* ' - 5.>- (. e:s e s

. :J -

g}s. g

., s:,~h.,.l'C.'*i?&t$ k,Y a,y..

l

....e

,.-.f.,t 4:.

...'31. :;.: '.,:

.; c n

I (E,!

Ts';.' :*.

a 3

(

\\

.l

.=

e s x

i ra

{

l-

&l$ f c-W h

i i

t

(

I l

l l

PENETRATION TEST l

f HEVISION O i

l

~

MAR.2 0 6 "

2-#2

. w' Type g-q vw e

- m-

- -. -a-a---a---w.

-.ww-e-ww u.ww- - - - -'--

AEiOO601 aEv.lOAvE cEscRier:ON MODEL CAPACITY CAP 5ULE STYLE DIM A DlM 8 (CURlE5)

(INCNES)

(lNCHE5)

A424-2 22 0001i GOCol N.A.

9 'MG A4 24 22 600lli60001 N.A.

Il'Ms A424-4 55 600111 60000 N.A 20 A4 24-5 6

600lI,60001 N. A.

7L M 24-7 165 600lR3 6 GCO2 N.A.

lTW A42A -8 IIO 600II > 60000 N.A.

II'5As A424 -l0 G

600ll > 60004 1.226 7%

A424 -Il 55 60011, 60004 1.225 9 SAs M24 -12 I10 60011, 60004 1 225 IO Ys

. A424 -13 350 60012, 60002 f 225 IO'5As 4424-14 l10 6001i, 6 0004 l.225 105/8 A424-l5 oI 600II s 60004 1.225 8ISAs A424 -16 53 6001Ii 60000 2.373 138/2 A424-17 33 600ll,G0000 2 373 13 %

A42$-18 55 600ll> 60000 I.225 10 %

A424-19

0. l i 6000l, 60004 f.229 7%

A453-1 IIO 60011s60 COO N.A.

Il'5Ag A473-2 l65 600lR.- 60002 N.A.

17'/4 A453 - 5 550 600l2, 60002 N.A.

Il4 A455-6 i10 0 600l3s 60043 N.A.

17 W

~

l A453 -7 l10 l

600lf s 60 COO N.A l liSAs A453 -8 90 6001I > 60000 M.A.

Il'She l

4453 -9 55 60011s 60000 2.373 13 W A453 - 10 55 6001i,60000 2.373 13 W l

B A

=

-F - -]25mQs/

[1

]

~

MATERIALS TECHNICAL OPER ATIONS INC.

RADIATION PRODUCTS DIVISION

- >~

BURLINGTON MA 01803 FINISH OWG TITLE

. n = -....

COBALT SOURCE REFERENCE

-~l'9 f h m.u n,=.x n

\\

CHECKE0 BY g

4 classification slZE DWG.NO.

R EV.

APPROVED BY GLES A

FRACTIONS i

\\

SCALE -

l SHEET I

OF 3 i

spautoma co. me. n soie.

PAGE 2-13

p,@{Ql R EY.

DATE DESCRIPVION INNER CAP 5uLE :

AGOOll-l A600ll-2

. A600ll-5

'N DlA A600 \\l-4

?A9

~ 4600ll-!li VA N

OUTER CAPSULE _

OUTEE PLUG

, 956

~ AGooll-G A600ll-6

=

6001)

. INNER CAPSULE:

A60012-I

- A6cor2-2 A60012 -5 y

- T

~

z

@\\\\\\W

./.

.350 y Ws\\\\\\%

\\

_.349 I

q CUTER CAP 5ULE

. l.2 79 r

OUTER PLUG A60Cl2-4 600\\2 A6 Col 2-4 INNEE CAPSULE escoa-5

~)

L a

/

.4 76 DIA u

_ \\

479

_j<

f

~

N OtJae CA50LE

[

- l588

=

B6005-3 OUTER PLLG 60013 i 860013-4 MATERIALS TECHNICAL OPERATIONS INC.

RADIATION PRODUCTS DIVISION

~

%g BURUNGTON, MA 01803 FINISH DWG TITLE g

COBALT SOURCE REFEEENCE DRAWN BY e

gggggw,tg,

M4r '<2<7s (DCUBLE ENCAP5ULATION)

.x

• s uHECKED BY y

/g CLASSIFICATION SIZE DWG.NO.

R EY.

m 2

/

APPROVED BY ANGLES A

FRACTICNS A

(

SCALE 2:1 l SHEET 2 OF 3 seauwiac co. ac. ai-sone, PAGE 2.

y-v,= -

R EV.

DATE DESCRIPTION A E CO 6 _O 476

_.250 p

_ 250 3 D-249

-249

.475 I

,v,

-A60003-2 fB60001-1 g

W

• Y

/

\\

, 9 65 937 A60000-1 f scoot-2 e

f T

iga 3 inaxa-I.

l p

A600009 y

\\ A50Cof 3 zy e

860000 860001

'A

~

A E 03-3 l

D e' 4g-D 9

+

~

~

B60005 g

AG00c2-2.

F1 y

_h.

/

~

A6COC2-1 g7

/

.96@

- o-Aam4-1 7

cars g

,lY A6 it b

5 b

i wM W

I j

l 860002 860004 i

l MATERIALS TECHNICAL. OPERATIONS INC.

RADIATION PRODUCTS DIVISION BURLINGTON, MA 01803 i

f, FINISH DWG TITLE 60 COBALT SOURCE REFERENCE DRAWN SY MS,sr 'N*n'a' acts ans 4 F4aa4 (SINGLE ENCAP5ULATION) 2 CHECKED BY y

,\\

g CLASSIFICATION SIZE DWG.NO.

REY.

k CPPROVED BY GLES FRACTIONS A SCALE 2: 1 l SHEET 3 OF 3 i

\\

PAGE 2-)5 sPauLDinG CO, anc. 2140169

3.

Thermal Evaluation 3.1 D!scussion The Model 770 is a completely passive device and has no mechanical cooling system nor relief valves. All cooling of the package is through0 free convection and radiation. The heat source is 550 curies of cobalt The corresponding decay heat is 9.18 watts.

3.2 Summary of thermal properties of Matetials The melting points of the materials used in the construction of the Model 900 are:

Steel 2453 F (1345 C)

Uranium 2070 F (1133 C)

Zirconium 3365 F (1852 C)

Copper 1981 F (1083 C)

Titanium 3308 F (1820 C)

The pofyurethane foam has a mini =um operating range of -100 F (-73 C) to 200 F (93 C).

It will decompose at the fire test temperature (800 C).

Decomposition will result in gaseous by products which will burn in air.

3.3 Technical Specification of Components Not Applicable 3.4 Normal Conditions of Transport 3.4.1 Thermal Model 60 The He#5 s urce in the Model 770 is a maximum of 550 curies of cobalt Cobalt decays with a total energy liberation of 2.82 MeV per disinte-gration or 16.7 millivatts per curie. Assuming that all of the decay energy is transf85med int heat, the heat generation rate for the 550 curies of cobalt would be 9.18 watts.

To demonstrate compliance with the requirements of paragrapbs 231 and 232 of IAEA Safety Series No. 6,1973 Edition for Type B (U) packaging, an analysis is presented in Section 3.6.1.

The thermal model employed

- is described in that section.

To demonstrate compliance with the requirements of paragraph 240 of LAEA Safety Series No. 6, 1573 Edition for Type B(U) packaging,,an analysis is presented in Section 3.6.2.

The thermal model employed is described in that section.

3.4.2 Maximum Temperatures The maximum temperatures encountered under normal conditions of transport will have no adverse effect on the structural integrity or shielding. As Revision 0 20 March 1981 3-1

3.5.4 Maximum Internal Pressures The Model 770 packaging is open to the atmosphere. Therefore, there will be no pressure buildup within the package. In Section 3.6.3, an analysis of the source capsule under the thermal test condition demon-stratesghat the maximum internal gas pressure at 800 C is 54 psi (373kN/m ).

Therefore, the maximum stress generated in the source capsule (containment) under the thermal test conditions would only be 5% of the yield strength of the material at the tast temperature.

3.5.5 Maximum Thermal Stresses There are no significant thermal stresses generated during the thermal test.

3.5.6 Evaluation of Package Performance The Model 770 will undergo no loss of structural integrity or shielding when subjected to the thermal accident condition. The pressure and tem-peratures have been demonstrated to be within acceptable limits.

.t-Revision 0 20 March 1981 3-3

3.6 Appendix 3.6.1 Model 770 Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 Edition 3.6.2 Model 770 Type B(U) Thermal Analysis: Paragraph 240 of IAEA Safety Series No. 6, 1973 Edition 3.6.3 Model 770 Type B(U) Source Capsule Thermal Analysis:

Paragraph 238 of IAEA Safety Series No. 6,1973 Edition

?

1 Revision 0 20 March 1981 3-4

3.6.1 Model 770 Type B(U) Thermal Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 This analysis dsmonstrates that the maximum surface temperature of the 50 C with the package in the shade and an Model 770 will not exceed,C.

ambiont temperature of 38 To assure conservatism, the following assumptions are used:

a) The decay heat load is assumed to be 10 watts.

b) The entire decay heat is deposited in the exterior faces of the Model 770.

c) The interior of the Model 770 is perfectly insulated and heat transfer occurs only from the exterior face to the atmosphere.

d) Because each face of the package eclipses a different solid angle, it is assumed that fif ty percent of the total heat is deposited in the top.

e.

The only heat transfer mechanism is free convection.

Using these assumptions, the maximum wall temperature is found from:

q = hA (T

-T) w a

Where q: Heat deposited per unit time in the face of interest (5 watts)

Free corvegtion hgat transfer coefficient h:

2 (1.38 (AT) W/m - C) 2 A: Area of the f ace of interest (0.356m )

T: Maximum te=perature of the wall of the package w

T: Ambient temperature (38 C) a From this relationship, the maximum temperature of the wall is 44.4 C.

This satisfies the requirement of paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973.

l l

l t

i i

Revision 0 20 March 1981 3-5 j

1 3.6.2 Model 770 Type B(U) Thermal Analysis Paragraph 240 of IAEA Safety Series No. 6,1973 This analysis demonstrates that the maximum surface temperatures of the Model 770 vill,not exceed 82 C when the package is in an ambient tem-perature of 38 C and insolated in accordt.nce with paragraph.240 of IAEA Safety Series No. 6, 1973.

I The calculational model consists of taking a steady state heat balance over the surface of the package. The following assumptions are used.

2

1) The package is insolated a3 the rate of 775W/m2 (800 cal /cm -12h) 2 on the top surface,194W/m (200 cal /cm - 12h) on the sides, and no insolation on the bottom.

2) The decay heat load is added to the solar heat load.

3) The package has a painted steel surf ace.

The solar absorptivi'ty is assumed to be 0.9.

The solar emissivity is assumed to be 0.8.

4) The package is assumed to undergo free convection from the sides and top, and undergo radiation from the sides, top and bottom. The inside faces are considered insulated so there is no conduction into the package. The faces are considered to be sufficiently thin that no temperature gradients exist in the faces.

5) The package is approximated as a rectangular solid 23in long, 24in wide and 20in higg. The surface areas of the top and bottom are each 0.356m.

2 The total surface area of the sides is 1.213m.

The maximum surface temperature is established from a steady starc heat balance relationship.

q in = q out

=9

+9 e

r Where q: Convective Heat Transfer qh Radiative Heat Transfer The heat load applied to the package is q in = a q, + qd Where a: Absorptivity (0.9) q: Solar heat load (511 watts) sq: Decay heat load (5 watts) i Revision 0 20 March 1981 3-6

(

l

~_

The convective heat transfer is:

e

{(hA) top + (hA) Sides }

(T -T) q

=

w a

c Where h: Convective heat transfer coefficient A: Area of surface of interest T,: Temperature of wall T,: Ambient Temperature J

The heat transfer due to radiation is:

,1 at A(t,4 - T,4) i q

=

r Where: c: Stefan Boltzmann Constant (5.669 x 10 gj,2,og)

-8 c: Emissivity (

0.8)

Iteration of this relationship demonstrates that the wall temperature of the Model 770 is 64.4 C which satisfies the require:nent of paragraph 240 of IAEA Safety Series No. 6, 1973.

J l

1 l

Revision 0 20 March 1981 l

1 3-7 r

I

3.6.3 Model 770 Type B(U) Source Capsule Thermal Analysis for Model 60000, 60001, 60002, 60004, 60011, and 60012 Source Capsules Paragraph 238 of IAEA Safety Series No. 6,1973 Edition This analysis demonstrates that the pressure inside the Model 60012 source capsule, when subjected to the thermal test, does not exceed the pressure which corresponds 'o the minimum yield strength of the material t

at the thermal test temperature. Since the other source capsules have diameters less than or equal to the diameter of the Model 60012 and have the same wall thickness, the maximum stress generated in the other source capsules will not exceed that of the Model 60012. The source capsules are fabricated from Type 304 or 304L stainless steel. The maximum out-side diameter of the Model 60012 is 0.35 inch (8.9mm). The source capsule is seal welded. The minimum weld penetration is 0.020 inch (0.5mm).

Under the conditions of internal pressure, the critical location for failure is this weld. The internal volume of the source capsule contains only cobalt metal as a solid, and air3 It is asgumed that the air is at standard temperature and pressure (20 C; 100kN/m ) at the time of loading This is a conservative assumption because, during the welding process, the internal air is heated, causing some of the air mass to escape before the capsule is sealed. When the welded capsule returns to ambient tem-perature, the internal pressure would be somewhat reduced. Under the conditions of paragraph 238 of IAEA Safety Series No. 6, it is assumed that the capsule could reach a temperature of 800 C (1474 F).

Using the ideal gas law and requiring the air to occupy a constant volume, the inter-nal gas presure could reach 373kN/m2 (54 psi).

The capsule is assumed to be a thin walled cylindrical pressure vessel.

The maximum longitidinal stress is calculated from:

aA = PA 7

p Where: c: longitud hal stress y

A: stress area = n(r

-r y) 7 g

P: pressure (373kN/m )

A: pressure area = nrg p

From this rglationship, the maximum longitudinal stress is calculated to be 1358kN/m (192 psi).

The hoop stress can be found by:

2o it = Pld; g

or c = Pr h

g t

Revision 0 20 March 1981 3-8

i Where: c: hoop stress h

t: vall thickness of the cylinder From this relationship, the hoop stress is calculated to be 2.89MN/m (418 psi).

At a temperature of 870 C (1600 F), the yield strength of Type 304 stainless steel is 69MN/m2 (10,000 psi). Thus, under the conditions of paragraph 238 of IAEA Safety Series No. 6,1973, the stress generated is less than 5% of the yield strength of the material.

l i

Revision 0 20 March 1981 3-9

4.

Containment 4.1 Containment Bcundarv 4.1.1 Containment Vessel l

The containment system for the Model 770 is the radioactive source capsule as shown in the descriptive assembly drawings in Section 2.10.

The source capsule is f abricated from either Type 304 or Type 304L stainess steel.

4.1.2 Containment Penetrations There are no penetrations of the containment.

4.1.3 Seals and Welds The containment is fabricated by General Electric Co. for Tech / Ops and is seal welded by a tungsten inert gas welding process according to Tech / Ops Standard Source Encapsulation Procedure (Section 7.4).

The minimum weld penetration is.020 inch (0.51mm).

4.1.4 Closure 4.2 Requirements for Normal Conditions of Transport 4.2.1 Release of Radioactive Material This source capsule has satisfied the requirements for special form radioactive material as delineated in IAEA Safety Series No. 6,1973 Edition and 10CFR71. Therefore, there will be no release of radio-active material under normal conditions of transport.

l

' Pressurization of the Containment Vessel 4.2.2 Pressurization of the source capsule under the conditions of the hypo-thetical thermal accident was demonstrated to generate stresses well below the structural limits of the capsule (Sections 3.5.4, 3.6.2).

Thus, the containment will withstand the pressure variations of normal transport.

4.2.3~ Coolant Contamination Not Applicable 4. 2.4 Coolant Loss Not Applicable Revision 0 20 March 1981 4-1 l

l

f 4.3 Containment Requirements for the Hypothetical Accident Conditions 4.3.1 Fission Gas Products Not Applicable 4.3.2 Release of Contents The hypothetical accident conditions of 10CFR71, Appendix B will result in no loss of package containment as described in Sections 2.7.7, 2.7.2 and 3.5.

i i

l l

l l

Revision 0 20 March ~1981

~

4-2

5.

Shielding Evaluation 5.1 Discussion and Results The Model 770 is shielded with 370 pounds of depleted uranium. The uranium shielding is cast around the.zircalloy or titanium source tube.

A radiatigg profile of Model 770, serial number 1 containing 427 curies of cobalt was made. The results of this survey are presented in Sec-tion 5g.1. Extrapoltation of this data to a capacity of 550 curies of 6

cobalt is presented in Table 5.1.

As the Model 770 has no neutron source, the gamma dose rates are the total dose rates which are presented.

As shown in Table 5.1, the maximum dose rates are below the regulatory requirements.

Table 5.1 Summary of Maximum Dose Rates (mR/hr)

At Surface At One Meter Side Top Bottem Side Top Bottom 168 35 52 6.45 2.71 2.58 5.2 Source Specification 5.2.1 Camma Source The gamma source is cobalt-60 in a sealed capsule as special form radio-active material in quantities up to 550 curies.

5.2.2 Neutron Source Not Applicable 5.3 Model Specification 5.4 Shielding Evaluation The shielding evaluation was 0erf rmed on Model 770, Serial No. I con-6 taining 427 curies of cobalt The results of this survey (Section

~ 5.5.1) demonstrate that the dose rates associated with this package are within the regulatory requirements. A radiation profile made on this package af ter being subjected to the hypothetical accident conditions (Section 5.5.2) show that there was no significant change in the shield-ing effectiveness.

Revision 0 20 March 1981 5-1

i 5.5 Appendix 5.5.1 Radiation Profile - Model 770 Serial Number 1 Before Drop and Puncture Tests.

5.5.2 Radiation Profile

.Model 770 Serial Number-1 After Drop and Functure Tests.

]

I I

l Revision 0 l

20 March 1981 l

5-2

Tech /Op3 Racaten Products Dmson 40 North Avenue Burington, Massachusetts 01803 Teephone (617) 272-2000 5.5.1 Radiation Profile Model 770 Serial Number 1 TOP RIGHT o

@ h 'N LEFT/ /'%

jf FFati Containing 427 Curies of Cobalt-60 Maximum Dose Rates (mR/hr)

@ Surface

@l Meter Top 27 2.1 Front 120 5.0 Right 42 2.2 Rear 130 5.0 Left 30 2.3 Bottom 40 2.0

(

Measurements were made with an AN/PDR-27(J) Survey Instrument l

l l

Revision 0 20 March 1981 5-3

Tech /Op2 Racaton Products Divisen 40 North Avenue Burnngton. Massachusetts 01803 Teiephone (617) 272-2000 5.5.2 Radiation Profile Model 770 Serial Number 1 (after drop and puncture tests)

TOP REAR RIGHT

/

LEFT m

Containing 391 Curies of Cobalt-60 Maximum Dose Rates (mR/hr)

@ Surface

@l Meter Top 25 2.0 Front 110 5.0 Right 35 2.2 Rear 100 5.0 Left 32 2.5 Bottom 48 2.0 Measuremets were made with an AN/PDR-27(J) Survey Instrument Revision 0 l

20 March 1981 i

5-4

l 6.

Criticality Not Applicable l

l l

l l

Revisica 0 20 March 1981 6-1 1

7.

Operating Procedures 7.1 Procedures for Loading the Package The source capsules are fabricated by General Electric Co. following Tech / Ops Standard Source Encapsulation Procedure. The procedures for fabricating the special_ form source capsule are presented in Section 7.4. The procedure for loading the source assemblies into the package is presented in Section 7.4.

7.2 Procedures for Unloading the Package The procedure for unloading the package is presented in Section 7.4.

7.3 Preparation of an Empty Package for Transport The procedure for preparation of an empty package for transport is pre-sented in Section 7.4.

w Revision 0 20 March 1981 7-1

}

7.4 Appendix l

7.4.1 Procedure for Encapsulation of Sealed Sources 7.4.2 Procedure for Receiving the Model 770 7.4.3 Procedure for Loading and Unicading the Model 770 e.

1 7.4.4 Procedure for Shipping the Model 770 i

t Revision 0 20 March 1981 l

s-7-2

7.4.1 Encapsulation of Sealed Sources A.

Personnel Requirements Only an individual qualified as a Senior Radiological Technician shall perform the opetations associated with the encapsulation of radioactive material. There must be a second qualified Radiological Technician available in the building when~ these operations are being performed.

B.

General Requirements The loading cell is designed to be operated et less than atmospheric pressure. The exhaust blower provided shall not be turned off except when the cell is in a decontaminated condition.

Sources shall not be stored in this cell overnight or when cell is unattended. Unencapsulated material shall be returned to the trans-far containers and encapsulated sources transferred to approved source containers.

When any of the "through-the-wall" tools such as the welding fixture or transfer plugs are removed, the openings are to be closed with the plugs provided. These tools shall be decontaminated whenever they are removed from the hot cell.

~ Preparatory Procedure C.

1.

Check welding fixture, capsule drawer and manipulator fingers from cell and survey for contamination. If contamination in excess of 0.001 pCi of removable contamination is found, these items must be decontaminated.

2.

If the welding fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this dummy capsule by sectioning thru weld. Weld penetration must be not less than 0.020 inch. If weld is sound and penetratica is at least 0.020 inch, the pre-paration of active capsules may proceed. If not, the condition responsible for an unacceptable weld must be corrected and the preparatory procedure repeated.

l 3.

Check pressure differential across first absolute filter, as measured by the manometer on the left side of the hot cell.

This is about % inch of water for a new filter. When this pressure differential rises to about 2 inches of water, the filter must be changed.

l l

Revision 0 l

20 March 1981 7-3 I

~

=

D.

Encapsulation Procedure 1.

Prior to use, assemble and visually inspect the capsule components to determine if weld zone exhibits any misalignment and/or separation. Defective capsules shall be rejected.

2.

Degrease capsule components in an Ultrasonic Bath, using isopropyl alcohol as degreasing agent, for g period of 10 --

minutes. Dry the capsule components at 100 C for a minimum of twenty minutes.

3.

Insert capsule components into hot cell with the posting bar.

4.

Place capsule in weld positioning device.

5.

Move drawer of socree transfer container into hot cell.

6.

Place proper amount of activity La capsule. Disposable funnel udst be used with pellets and a brass rivet with wafers to prevent contamination of weld zone.

7.

Remove unused radioactive material from the hot cell by withdrawing the drawer of the source transfer container from the cell.

8.

Remove funnel or rivet.

9.

Assemble capsule components.

10. Weld adhering to the following conditions:

a.

Electrode spacing.021" to.024" centered on joint +.002"; use jig for this purpose.

b.

Preflow argon, flush 10 seconds.

I l

c.

Start 15 amps.

l d.

Weld 15 amps.

e.

Slope 15 amps.

11. Visually inspect the veld. An acceptable weld must be continuous without cratering, cracks, or evidence of blow out. If the veld is defective, the capsule must be cleaned and revelded to accept-able conditions or disposed of as radioactive waste.

I

12. Check the capsule in height gauge to be sure that the weld is at the center of the capsule.

13. Wipe exterior of capsule with flannel patch wetted with EDIA l

solution or equivalent.

l Revision 0 20 March 1981 7-4

14. Count the patch with the scaler counting system. Patch must show no more than.005 pCi of contamination. If the patch shows more than.005 pCi, the capsule must be cleaned and reviped. If the rewipe patch still shows more than 0.005 pCi of contamination, steps 8 through 11 must be repeated.

15. Vacuum bubbic test the capsule. Place the welded capsule in a glass vial containing ixopropyl alcohol. Apply a vacuum of 15in Hg(Gauge). Any visual detection of bubbles will indicate a leaking source. If the source is determined to be leaking, place the source in a dry vacuum vial and boil off the residual alcohol. Reweld the capsule.

I

16. Transfer the capsule to the swaging fixture. Insert the wire I

and connector assembly and svage. Hydraulic pressure should not be less than 1250 nor more than 1500 pounds.

17. Apply the tensile test to assembly between the capsule and connector by applying proof load of 75 lbs. Extension under the load shall not exceed 0.1 inch. If the extension exceeds 0.1 inch, the source must be disposed of as radioactive waste.

18.

Position the source in the exit port of hot cell. Withdraw all personnel to the control area. Use remote control to insert source in the ion chamber and position the source for maxinnam response. Record the meter reading. Compute the activity in curies and fill out a temporary source tag.

19. Using remote control, eject the source from cell into source changer through the tube gauze wipe test fixture. Monitor before reentering the hot cell area to be sure that the source is in the source changer. Remove the tube gauze and count with scaler counting system. This assy must show no more than 0.005 pCi. If contamination is in excess of this level, the source is leaking and shall be rejected.

20.

Complete a Source. Loading Log for the operation.

i l

l l

Revision 0 20 March 1981 i

7-5 t

7.4.2 Receiving Radioactive Material The consignee of a package of radioactive material must make arrange-ments to receive the package when it is delivered. If the package is to be picked up at the carrier's terminal,10CFR Part 20.205 requires that this must be done expeditiously upon notification of its arrival.

If damage is evident, the carrier's agent should be present while un-loading. Survey the container with a survey meter as soon as possible, preferably at the time ci pickup and no more than three hours later if ic was received during working hours, or no more than 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> later if it was received af ter normal working hours. Radiation levels should not exceed 200 milliroentgens per hour at the surface of the container nor 10 milliroentgens per hour at a distance of three feet from the surface. Actual radiation levels should be recorded on the receiving report. If the radiation levels exceed these limits, the container should be secured in a Restricted Area, and the appropriate personnel notified.

The source isotope, activity, model number and serial number and the shipping container Model 770 and serial number should be recorded in the receiving report.

l l

l Revision 0 20 March 1981 I

7-6 t

7.4.3 Procedure for Loading and Unioading Source Changers Source changes may be performed only in a properly secured Restricted Area. To perform a source change, the operator must wear a pocket dosimeter with a range of zero to at least 200 milliroentgens that is recharged at the start of every shift, and a film badge or ILD. The radiographer must also have a survey meter capable of measuring from 2mR/hr to at least 1000mR/hr in order to determine radiation levels.

The radiographer or radiographer's assistant must guard against unacch-orized entrance into the secured areas at all times. No personnel should be allowed into the Restricted Area without a direct reading pocket dosimeter and either a film badge or TLD.

To perform a source change, do the following:

1) Survey the Model 770 source changer to ensure the source is in the proper storage position.

2) Position the Model 770 source chenger and exposure device close together so that one section of source guide tube will connect them with no sharp turns or bends. The bend radius of the guide tube should never be less than twenty inches. Shorter bend radii can restrict source movement in the source guide tube.

3) Remsve the storage plug from the exposure dev-ice, and attach the source guide tube. Remove the cover from the source changer and attach the other end of the tube to the empty chamber cf the source changer.

4) Attach the control unit to the exposure device according to the procedure for that exposure device.

5) Crank the source rapidly from the exposure

~

device to the source changer.

During this process, the survey meter reading should increase the source is first exposed, fall slightly as the source is being cranked out, then drop to background when the source is in the source changer.

6) Approach the source changer and source guide tube with the survey meter to ensure that the source is fully within the source changer.

Revision 0 20 March 1981 77

7) Disconnect the source guide tube from the source changer and disconnect the drive cable from the source assembly by moving the lock pin down and sliding the drive cable connector ball out through the key way.

8) If a replacement -source :is to be installed in the exposure device, couple the drive cable to the new source assembly and connect the source guide tube to the connector assembly on the source changer.

9) Return to the controls and crank the new source into the exposure device. The survey meter should increase as the source leaves the source changer and approaches the exposure device, then drop to background level when the source is shielded in the exposure device.

10) Survey the exposure device to ensure that the process has been properly completed. Radiation levels should read no more than 200mR/hr at the surface of the exposure device. Secure the source in the exposure device.

11) Survey the source guide tube and source changer to check that the source has been correctly trans-ferred.. Radiation levels should not exceed 200mR/hr at the surface of the source changer, nor 10mR/hr at three feet from the surf ace.

12) Secure the source (s) in the source changer by turning the connector selector rings to LOCK, depressing the lock plungers, and removing the keys.

13) Disconnect the control unit and source guide tube from the exposure device as in step 4 and disconnect the source guide tube from the source changer.

l

14) Remove the source identification plate from the exposure device and attach it with seal wire to the connector assembly.

15) Affix the identification plate of the new source to the exposure device.-

Revision 0 20 March 1981 7-8

M e s 4~. 9

.:Q> '

d

////Q

1. y >

y,,

TEST TARGET (MT-3) 1 1

1.0 52 m a m p#2 I H.A t in lj12.0'Il-ii 5_

1.1 w.

l.8 1.25 I IA i

I

.6

-1 a!

/

g l

• t4

+

Ayy

%'p,;,9z7zz

+p.;;r &xs

/

y s

< p ; 3' 4

%//(ff sps//,s'NNN ~ 44 s/// < s w 7 DA / . w% j ' i /4hRy: &(c*4 a 7.4.4 Shipping Radioactive Material The Model 770 meets the requirements for a Type B shipping contaiaer under the regulations of the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and the International Atomic Energy Agency. The container has been assigned USNRC Certificate of Compliance No. for domestic shipments and IAEA Certificate lo. USA / / B(U)T for international shipments. The following shipping procedures comply with NRC Regulations 10CFR Part 71 and DOT Regulations 49CFR Parts 171 through 179 regarding the transportation of radioactive materials.

1) Ensure that the source is locked into place in its storage position. To check this, the lock should be in the down positica, and the selector ring should be immobile. Secure the cover plates to the container, and seal wire the eight hex head bolts to provide a tamper proof seal.

2) Perform a radioactive contamination wipe test of the outer shipping package. This consists of rub-bing filter paper or other absorbent materia}, using) neavy finger pressure, over an area of 100cm (16in of the package surf ace. The activity on the filter paper should not exceed 0.001pCi of removable con-tamination.

3) Survey the package with a survay meter at the sur-face and at a distance of three feet from the surface to determine the proper radioactive shipping labels to be applied to the package as required b~y 49CFR Part 172.403. The radiation exposure limits for each shipping label are given in Figure 7.1.

If radiation levels above 200mR/hr at the surface or 10mR/hr at three feet from the surf ace are measured, the container must not be shipped. I

4) Properly complete two shipping labels indicating the radioactive isotope, activity and the Transport Index. The transport Index is used only on Yellow II and Yellow III labels and is defined as the max-imum radiation level in milliroentgens per hour measured at a distance of three feet from the sur-face of the package. Put these two labels on opposita sides of the container after making sure any previous labels have been removed. The package should be marked with the proper shipping name (Radioactive Material, Special Form, n.o.s.).

If Revision 0 20 March 1981 7-9 Table 7.1 Radiation Exposure Levels '#8 3 Feet RACICACTIVE-WHITE I 4.4 4 Nmw RADIOACTIVE I / ,/ / RACICACTivE-YELLOW tt 4.4 a

• ^ "

RlA l0 ACTIVE li/ W e' ss RACtCACTIVE-YELLCW tu d.k 'nu RADIDACTIVElil _./ \\ / f' 7 - 9a the exposure device is packaged inside an outer container, mark the outside package "INDIDE PACKAGE COMPLIES WITH PRESCRIBED SPECIFICATIONS - TYPE B USA / /B(U)".

5) Complete the shipping papers indicating:

Proper shipping name (Radioactive Material, a. Special Fo m, n.o.s.) b. Name or Radionuclide ( Cobalt) Physical or chemical form (special form) c. d. Activity of Source (expressed in curies or millicuries) Category of Label Applied (i.e. Radioactive e. Yellow III) f. Transport Index g. USNRC Identification Number of DOT Specifica-tion Number (USNRC: USA / /B) h. For export sh*pments, IAEA Identificction Number ( IAEA: USA / /B)

i. Shipper's Certification:

"This is to certify that the above named materials are properly classified, described, packaged, mark-ed and labeled and are in proper condition for transport according to the applicable regulations of the Department of Transportation." Notes: 1. For air shipments, the following l shipper's certification may be used: l l l "I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are classified, packed, marked and labeled and are l in proper condition for carriage by air according to applicable national governmental regulations." l 2. For air shipments, the package must be labeled with c. "CARCO AIRCRAFT ONLY" label and the shipping papers must state: l ~ "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRESCRIBED FOR CARCO-ONLY AIRCRAr7" I Revision 0 8 7 - 10 20 March 1981 o. 7.4.5 Shipment of E=pty Container

1) Ensure that the source is secured in place, and the connector assembly is in the LOCK position with the lock plunger in the down position and the key re=oved, secure each side cover to the outer container with the eight attaching hex head bolts, and secure the bolts with seal wire.

2) Mark the outside of the cuter shipping package:

"RADI0ACIIVE -MATERIAL - LSA, n.o.s.".

3) Perform a radioactive conta=ination vipe test of the shipping package and ensu:e that the wipe test does not exceed 0.001 =icrocuries per 100 square centimeters.

4) Survey the package at the surface and at threc feet fro = the surf ace to deter =ine the proper radioactive shipping labels to be applied to the package.

a. If the surface radiation level is less than 0.5 milliroentgens per hour and there is no measur-able radiation level at three feet from the sur-f ace, no label is required. Mark the outside of the package with the statement: "Exe=pt fro = specification packaging, marking and labeling, and exe=pt from the provisions of 49CFR173.393 per 49CFR173.391(c). Exe=pt from the require =ents of 49CFR Part 175 per 49CFR175.10(s)(6)." Properly cocplete the shipping papers: (1) Proper shipping name (Radioactive Material LSA, n.o.s.) (2) Name of Radionuclide (Depleted Uraniu=) (3) Physical or Che=ical Form (Solid Metal) (4) Activity (in curies or millicuries) (5) The statement " Exempt from specification packaging, marking and labeling, and exe=pt from the provisions of 49CFR173.393 per 49CFR173.391(c). Exempt from the require-ments of 49CFR Part 175 per 49CFR175.10(a)(6)." Revision 0 20 March 1981 7 - 11 e. (6) Shipper's certification: "This is to certify that the above named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transport according to the appli-cable regulations of the Department of Trans-portation." NOTES: (1) For Air Shipments, the following shipper's certification may be used: "I hereby certify that the contents of this consignment are fully and accurately described above by proper shipping name and are class-ified, packed, marked and labeled and are in proper condition for carriage by air according to applicable national governmental regulations." (2) For Air Shipments, the following statement must appear: "This shipment is within the limitations pre-scribed for passenger aircraft in accordance with 49CFR175.10(a)(6)." b. If the surface radiation level exceeds 0.5 mill-roentgens per hour, of if there is a measurable radiation level _ac three feet from the surface, ~ use the criteria of Table 7.4.2 to determine the proper radioacti' e shipping labels to be applied to the package. Complete thi shipping papers indicating: (1) Proper Shipping Name (Radioactive Material, LSA, n.o.s.) (2) Name of Radionuclide (Depleted Uranium) (3) Physical or Chemical Form (Solid Metal) (4) Activity (In Curies or Millicuries) (!,) Category of Label Applied (i.e. Radio-active Yellow II) (6) Transport Index (7) USNRC Identification Number (USNRC USA / /3) (8) For Export Shipments, LAEA Identification Number ( IAEA USA / /3) (9) Shipper's certification: Revision 0 20 March 1981 7 - 12 j "This is to certify that the above named materials are properly classified, described, packaged, marked and labeled and are in proper condition for transport according to the appli-cable regulations of the Department of Trans-portation." NOTES: (1) For Air Shipments, the following shipper's certification may be used: "I hereby certify that the contents of this consignment are fully and accurately des-cribed above by proper shipping name and are classified, packed, marked and labeled and are in proper condition for carriage by air according to applicable national governmental regulations." (2) For Air Shipments, the package must be labeled with a " CARGO AIRCRAFT ONLY" label and the shipping papers must state: "THIS SHIPMENT IS WITHIN THE LIMITATIONS PRE-SCRIBED FOR CARGO-ONLY AIRCRAFT." l l Revision 0 20 March 1981 7 - 13 8. Acceptance Tests and Maintenance Program 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure proper assembly and that the package is properly marked. The seal weld of the radioactive source capsule is visually inspected for proper closure. 8.1.2 Structural and Pressure Tests The source assembly is subjected to a static tensile test with a load of seventy five pounds. Failure of this test will prevent the source assembly from being used. 8.1.3 Leak Tests The radioactive source capsule (the primary containment) is wipe tested for leakage of radioactive contamination. The source capsule is also subjected to a vacuum bubble leak test. These tests are described in Section 7.4. Failure of any of these tests will prevent use of this source capsule. 8.1.4 Component Tests The lock asse=bly of the package is tested to assure that the security of the source asse=bly will be maintained. Failure of this test will prevent use of the package until the lock assembly is corrected and retested. 8.1.5 Tests for Shielding Integrity l The radiation levels at the surface of the package and at three feet from the surf ace are measured using a small detector survey instrument i (i.e. AN/PDR-27). These radiation levels, when extrapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour at the surface nor 10 milliroentgens per hour at three feet from _ the surface of the package. Failure of this test will prevent use of i the package. 8.1.6 Thermal Acceptance Test Not Applicable j 8.2 Maintenance Program t 8.2.1 Structural and Pressure Tests Not Applicable i Revision 0 20 March 1981 i 8-1 1 ( 8.2.2 Leak Tests As described in Section 8.1.3, the radioactive source assembly is leak tested at manufacture. Additionally, the source assembly is wipe tested for leakage of radioactive contamination every six months. 8.2.3 Subsystem Maintenance The lock assembly is tested as described in Section 8.1.4 prior to each use of the package. Additionally, the package is inspected for tight-ness of fasteners and general condition prior to each use. 8.2.4 Valves, Rupture Discs and Gaskets Not Applicable 8.2.5 Shielding Prior to each use, a radiation survey of the package is made to assure that the radiation levels do not exceed 200 milliroentgens per hour at the surf ace nor ten milliroentgens per hour at three feet from the sur-face. 8.2.6 Thermal Not Applicable 8.2.7 Miscellaneous Inspections and tests designed for secondary users of this package under the general license provisions of 10CFR71.12(b) are included in Section 7.4. Revision 0 20 March 1981 it '113 8-2 l .