ML20023D575

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Forwards Revised Info Re Model GNG-20 Source Container
ML20023D575
Person / Time
Site: 07109163
Issue date: 04/28/1983
From: Hopcraft C
GULF NUCLEAR, INC.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
22268, NUDOCS 8305240031
Download: ML20023D575 (35)
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2 202 MEDICAL CENTER BLVD. WEgjTg'[fXgg98 (713)332-3581 y! Eke

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-jo 3%s s April 28, 1983 O

p DOCKETD) 1 URC Mr. Charles E. MacDonald s

Chief MAY1g IOO3 b 8

Transportation Certification Branch 76 g,m Division of Fuel Cycle and ud'L Stenou S'

Material Safety, NMSS s

DOCxtTCitex United States Nuclear Regulatory s'

Commission t

..;\\O Washington, D.C.

20555 3E:

DOCKET #71-9163

Dear Mr.-MacDonald:

Please accept these contents as the required revision for the Model GNG-20 source container.

DOCKET MODEL INITlAL NRC APPL.

PERSONAL NRC s

NUMBER APPL.

LETTER

RESPONSE

VISIT LETTER 71-9163 GNG-20 3/2/82 5/14/82 1/28/83 3/17/83 3/22/83 Pages 1 through 9 are revised, Appendix 1, 1(a), 1(b), 1(c) are redrawn _and pages 18, 19, and 20 are additional.

I hope that this meets with your approval and we obtain the necessary certification for this container as soon as possible.

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If more information is needed, please contact me.

c Respectfully.

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TABLE OF CONTENTS

.I PAGE o.

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[ ; 1.

GENERAL INFORMATION..............................

1 L

1.1 ; Introduction................................

1

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2.

PACKAGE DESCRIPTION..............................

1 a-g j.. &.4 t2. 2.

Package.....................................

1

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2.1 A

Contents....................................

1 e

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STRUCTURAL EVALUATION............................

1 3?-

M 3.1 Discussion..................................

1 3.2 Design Criteria.....................

2 s

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.a 3.3 Weight......................................

2 3.4 Mechanical Properties of Materials..........

2 (O

3.5. Chemical and Galvanic Reactions.............

2 3.' 6 Po s istiv e Closure.............,..............

2 3.,7 L i f ti i n g D e v i c e s............................. 2

+

3.8 Tie'Down Devices............................

3 fl 3.9 Structural Standards........................

3 7..

3.10 Standards for Normal Conditions of Transport 4

~4.

liYPOTilETICAL ACCIDENT CONDITIONS.................

5

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4.1 Free Drop...................................

5 3

M 4.2 Puncture....................................

5 4.3 Thermal Test..................:.............

5 g

Results..........................................

6 i

5.

OPERATING PROCEDURES.............................

7 1

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5. l, Procedures for Loading the GNG-20...........

7

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5,.,2 Procedures for Unloading the GNG-20.........

7 eC, t

,16. I ' A C C E P T A N C E T E S T S................................. 8 7.

MAINTENANCE PR0 GRAM..............................

9 s

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ji APPENDIX

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DRAWING OF GNG-20................................

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1(a)

Detailed Drawing of GNG-20 Shield..........

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Detailed: Drawing of Insert for GNG-20 g

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PAGE 4

2.

' PICTURES 0F FREE DROP TEST......................

6-7 l

2(a)

' Corner Free Drop; Test.....................

8'- 9 2(b)

Free' Drop Test onto Closure End...........

10 3

3.-

PUNCTURE TEST...................................

11-13 t-

- 4.

THERMAL TEST,...'....................'............

14-18 5.

-FIRE TEST FOR SHIELD............................

19

' 6.

APPROVAL LETTER FOR MODEL 71-2A.................

20 I

7.

WITNESS.........................................

21 9

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GENERAL INFORMATION i

The enclosed information concerns a metal container which weighs three hundred pounds and is to be used to transport an-Americium-241/ Beryllium neutron source.

s

1.1 INTRODUCTION

The container, Model GNG-20, will be used to transport a 20 curie Americium-241/ Beryllium neutron source, Gulf Nuclear, Inc. Model 71-2A.

The GNG-20 with a 20 curie AmBe source, Gulf. Nuclear, Model 71-2A in place, has a transport index of approximately 3.

The container is cylindrical in shape and lies in a horizontal position.

The container has been painted safety purple.

2

-PACKAGE DESCRIPTION 2.1 Package The GNG-20 is constructed of cold rolled, ten gauge steel and has outer dimensions of twenty inches in diameter and twenty inches in length.-

The container is filled with a 60-40 weight percent of hydrated boric acid and polyester OE resin weighing approximately 11 pounds / gallon.

There is an internal cavity that is designed to accept the 71-2A, 20 curie Americium-241/ Beryllium source which is. held in

. place with 5/8 inch stub acme threads.

The female portion of the thread is part of the container and the male portion is on the source.

It is impossible to remove

the source without a handling tool.

Detailed.information concerning dimensions and other fabrication details contained in Appendix 1.

are 2.2 Contents of Package The GNG-20;contains curies of Americium-241. source which may contain up a

to 20 Containers will be used to trans-port Gulf Nuclear, Inc. AmBe sources, source Model 71-2A.

3 STRUCTURAL EVALUATION 3.1 Discussion The GNG-20 container's basic integrity is due to the fact that the structure is a metal cylinder completely filled with a solid material.

The solid material, hydrated boric acid which has been dispersed in-polyester. resin, is self-extinguishing.

O (1).

. REVISION-1: 4/20/83,

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3. 2-Design' Criteria

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Since the. radiation level of a 20 curie AmBe neutron source is low compared - to ' the normal Type B quantities, i.e.. gamma

' emitters ~ such as Iridium-192, the major criteria for the neutron shield is simply a combination of hydrogenous material and distance from the source required to meet shippingfrequirements.

The physical structure of the container is very simple'and its mechanical strength is demonstrated by the results of the drop test.

3.3.

Weight The weight of the package is three hundred (300) pounds.

f.

3.4 Mechanical Properties of Materials All-metal components of the container are fabricated from mild steel.-.The shielding material is a 60-40 mixture by weight, hydrated boric acid and polyester resin.

3.5 Chemical and Galvanic Reactions The radioactive sources, Gulf' Nuclear, Inc. Model 71-2A, are fabricated using 17-4 PH stainless steel.

There is no reaction between the stainless steel and the mild steel.

Long t'erm usage of existing containers do not. indicate a

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problem with internal corrosion between acid _and the mild Nl steel structure.

3.6 Positive Closure The sealed source cannot be exposed without removing a key operated padlock.

There is water tight integrity inside the containerfprovided by the rubber seal between the door and the door opening.

The retaining pin is constructed to act1as a lever on the door to-apply pressure on the rubber seal which' insures the water tight integrity.

~

3.7 Lifting Devices There.are four-(4) handles (two on each' side) welded to the container of which anyone is capable of withstanding.

the weight of the container (referfto Appendix 1).As shown

.in photograph P.13, any handle will withstand three (3) times the weight.of.the container.

Failure of the device willlnot impair the. containment or shielding properties of Lthe package. 'This is demonstrated by deliberately beating-a handle.off the container'with a sledge hammer (see results;" photograph

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REVISION 1: 4/20/83 i'

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3.8

. Tie-Down Devices

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$The 1egs-of,the container are welded to the main body J and are equipped to receive 4 - 5/8-11 NC bolts.

When used as a. tie-down. device, the container is bolted to Lthe floor of the transporting vehicle using 2" long x 5/8-11 NC-bolts.

The load required to break ~one 5/8-o UNC. thread is' calculated at 13,500 pounds.

The shear l

strength for steel is 0.75Ltimes the tensile strength

(

Reference:

Machinery's Handbook, 21st Edition, pp. 444) which for SAE 570 is of minimum 60,000 pounds /in.e.

Therefore, with a shear strength of 45,000 pounds, this is over 150 times ti - weight of the container.

Therefore the mounting ~1egs of.the container meets the requirements l

of 10 CFR 71.31'(d).

3.9 Structural-Standards for Type B and Large Quantity Packaging i

3.9.1 Load Resistance j'

The container is considered as a simple beam with the L

outer container the sole structure member, and supported

.at.both ends.

.If a uniform load of five times the

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container. weight is evenly distributed along its length,

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the{ maximum stress can be computed from:

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.sj MAX. STRESS WL

=

8Z Total Load-(1500 lbs.)

W

=

Length of beam (20 inches)

L

=

Section Modulus (314.15 in.3)

Z

=

l-l

(

Reference:

Machinery's Handbook, 21st Edition, pp.404)

L The ~ container is circular in shape, twenty (20) inches in diameter and twenty (20) inches long with a wall thickness of.25 inches..

Using this formula, the maximum stress generated in the beam is 67.48 pounds per square inch, which is below'thefyield strength of steel (30,000-to 70,000 pounds per' square inch).

3.9.2.

External Pressure The GNG-20 is open to the air,'therefore there will'be no differential pressure to.act upon the container.

The source'(Model'#71-2A)Lis' contained in'a stainless steel bull plugowhich.is designed to ~ prevent pressure upon.the source.

Nevertheless,.all sealed sources manufactured in Texas must-

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be pressure test 2d to 25,000 psi,.TRCR 36.108(a)(3).

.(3)

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REVISION. 1:4/20/83 w.

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- s 3.10 Normal Conditions of Transport

/~T 3.10.1 Heat N,.]

The thermal evaluation of the Model GNG-20 is presented

-in Section 4.3.

From-this evaluation, it can be concluded that-it can. withstand the normal heat conditions as specified in 10CFR Appendix A.

3.10.'2 Cold The metals used in the GNG-20 can withstand temperatures of-40oC.

The lower limits of the resin is -40 C.

Therefore, the container can withstand the normal transport cold condition.

3.10.3 Pressure The GNG-20 is open to the atmosphere, therefore, there will be no pressure differential acting upon it.

The source capsules are all tested to 25,000 psi.

(See 3.9.2).

3.10.4 Vibration These containers have been in use as Type A containers for 6 years without a failure due to vibration.

The only movable parts are the locking pin, held in place by a

)-

safety pin, the door, held in place by the locking pin, kJ the insert, held in place by the door, and the bull plug containing the source which is screwed into the container.

This container can withstand vibrations normally associated with transport.

3.10.5 Water Spray

.All materials used in the construction of the Model GNG-20 are water resistant.

Exposure to water will not affect the structural integrity or reduce the shielding effective-ness of the container.

3.10.6 Free Drop The results of the free drop test performed is the Hypothetical Accident Conditions (Section 4.1) prove the GNG-20 will with-stand the normal transport free drop condition without loss of shielding effectiveness or loss of structural integrity.

4 3.10.7 Corner Drop Does not apply.

. rm (4)

()

REVISION 1:4/20/83

m-6

'3.10.8 Penetration-

. A);:

T The hemispherical end of a l'1/4" diameter steel rod weighing 15-pounds was dropped from a height of 40 inches onto both ends-and one side of the container with no physical damage to the container and no change in the shielding properties.

The container withstood the puncture test for the Hypothetical Accident Conditions (See Section 4.2).

3.10.9 Compression The container was subjected to 8 times its own weight for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with no change in the physical and shielding properties (See Photograph P.18).

4 HYPOTHETICAL ACCIDENT CONDITIONS 4.1 -

Free Drop

-The GNG-20 was dropped thirty (30) feet onto a k inch steel

- plate supported by an eight (8) inch thick concrete pad and sustained'little damage.

There was no change to the shielding and contaiament characteristics.

(See Appendix 2).

The con'tainer was; dropped thirty (30) feet onto a corner and g

although physical damage occurred, the containment of the

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source was not-changed, nor was there any change in the shielding properties of the container.

(See Appendix 2a).

The container was dropped thirty (30) feet onto the closure end and although there was physical damage, the containment

- and shielding properties did not change.

(See Appendix 2b).

4.2 Puncture The container was dropped forty (40) inches onto a six '(6) inch diameter bar, eight (8) inches long on three (3) different occasions (1) flat, (2) closure end and (3) on a welded corner.

Physical damage' occurred, but the containment of the source and the shielding properties of the container were not changed.

(See Appendix 3).

Throughout all the drop tests, a standard container was used.

A standard container weighs three hundred (300) pounds.

4.3 Thermal-Test The GNG-20 container.was suspended over a six (6) foot diameter tank _containing water with diesel fuel floating on the water (see diagram).

The fuel was ignited and kept_ burning for thirty.(30). minutes by pumping more fuel.

The temperature was s

(5)

REVISION 1:4/20/83

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7 I h monitored to insure that at least fourteen hundred seventy-p five (1475) degrees F.

or 801 degrees C.

was maintained Q

throughout the test.

Gases were emitted from the container and burned.

These gases are vented through holes in the container provided for this purpose.

These holes are covered by identification tags during normal use, but are thrust aside when the gases are generated within the container.

The gases burned during the-test, but ceased to burn within five (5) minutes.after the fire was extinguished.

The fire was extinguished by shutting off the fuel supply.

The container was allowed to cool naturally.

4.3.1 Results The container had deformation due to the heat and expanding gases, but the contents of the container-remained intact.

Some loss of shielding occured from the thermal test, but the radiation level remained within the Yellow III shipping values (see below).

Radiation Levels Before Tests mrem Surface mrem at 36 inches Neutron Neutron Top 43.3 5.4 Bottom 44.6 4.7 f

Front-Door Closed Q

+ Insert 34.2 4.0 Front-Door Open Insert 85.3 19.0 Left Side 38.7 5.2 Right-Side 47.0 5.2 Back 62.6 6.9 Radiation Levels After Tests Top 88-7.2 Bottom 84 7.9 Front 150 9.0 Front Door Open - Insert 280

'150.0 Back' 84 6.5 Left Side 88 7.2 Right Side 100 7.3 m-

- (..)

(6)

REVISION 1: 4/20/83 L

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OPERATING PROCEDURES

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5.1 Procedures for Loading the GNG-20 (1)

Remove the safety pin from the lock pin.

(2)

Rotate the lock pin 180 degrees, being certain the flat side of the lock pin is against the door.

(3)

Remove the lock pin.

(4)

Open door.

(5)

Remove the insert from the cavity.

(6)

Using an adequate length handling tool (recommend 5 feet); place bull plug in cavity.

(7)

Secure bull plug in cavity by turning handling tool clockwise, engaging the threaded portions of the bull plug and the container.

(8)

Make hand tight plus 1/4 turn.

(9)

Place insert in cavity.

(10)

Close Door.

(11)

Place lock pin in position with flat side of pin against the door.

(12)

Rotate lock pin 1800 degrees, compressing foam rubber material between door and face of container insuring water tight integrity.

(13)

Secure lock pin in place.

(14)

Put safety pin in lock pin.

(15)

Secure container with padlock through hasp on door.

(16)

Check container with survey meter at surface and at

(

1 meter to insure conformance with the radiation limits in 49 CFR Part 172.

5.2 Procedures for unloading the GNG-20 Upon receiving a container, it must be checked for possible contamination and radiation levels as required in 10 CFR 20.205.

If contaminations or radiation levels are in excess of the specified limits, the required notifications will be made (as per 10 CFR 20.205).

If the container meets the specified limits, the following procedures will be used in unloading the container:

(1)

Using the provided key, unlock the padlock and remove.

(2)

Remove the safety pin from lock pin.

(3)

Rotate the lock pin 180 degrees.

(4)

Remove lock pin.

(5)

Open door.

(6)

Remove insert.

(7)

Attach handling tool to bull plug.

(8)

Rotate handling tool counter clockwise a sufficient number of turns to free threads on bull plug from container.

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(7)

REVISION 1:4/20/83

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(9)

Being certain area--is clear of non-necessary personnel remove bull plug from container.

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(10)

Secure bull plug to logging tool or'if the source is being put in storage place in secure place.

(11)

After'the bull plug is removed the container will be; checked for contamination.

The surface of the container must have no significant radioactive contamination as provided in 49 CFR 17 3. 3 9 7 (a ).

6 ACCEPTANCE TESTS All containers of these designs will be manufactured and used-in accordance with Gulf Nuclear, Inc.'s Quality Assurance Program.

6.1.1 Visual Inspection The container is visually examined to insure proper assembly and properly marked.

6.1.2 Structural Tests All. prototypes _of each container are subjected to the Appendix A - Normal Conditions of Transport and Appendix B -

['N Hypothetical Accident Conditions tests before production is started.

6.1.3 Leak Tests All manufactured sources will be subjected to leak tests prescribed for special form sources in IAEA Safety Series 6,

1973 Edition And/or the USA Regulations in 49 CFR Part 173.

Failure of any of these tests will prevent the use of the source.

6.1.4 Component Tests All components used in the manufacturing of this container are tested for proper fit and operation before leaving the manufacturing plant.

After being received from the paint shop and put in the warehouse the mechanical parts of the container are again tested for proper functioning.

6.1.5 Tests for Sheilding Integrity The radiation levels at the surface and 1 meter from the surface are_ measured with a gamma and neutron meter before being put in use..

The combined radiations must not exceed 200 millirems / hour. at the surface and 10.0 millirems / hour j'T at 1 meter.

Failure of this test will prevent the use A>

_of-_the container.

(8)

REVISION 1:4/20/83 l

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Not applicable..

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.7-MAINTENANCE PROGRAM 7.1.1 -

Structural and Pressure Tests Not applicable..

-7.1.2

-Leak Tests

'See Section 6.1.3.

7;1.3 Subsystem Maintenance All moving parts are check as'per section 6.1.4 before being put in use.

I-

.7.1.4 Valves, Rupture Discs and-Gaskets I:

The rubber: gasket used in maintaining the water tight-integrity is checked for resiliency and replaced if not

,, 4 performing as needed.

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Shielding 7.1.5

~

'Before. shipping any source the surface and 1 meter r:41ation levels are checked.

If 200. millirems / hour at surface millirems / hour-at.one meter are exceeded, the container-or-will not be used.

7.1.6 Thermal Not applicable.

7.1.7 Miscellaneous

'Not applicable.

(9)

REVISION 1:4/20/83

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l REVISIONS NO.

DATE BY_

GULF NUCLEAR,INC.

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GNG-20 INS ERT DETAIL 3

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'MM'D ATE 6-4-82 DRAWING NO.

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The GNG-20 (on left) Prior

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l l

APPENDIX 2a CORNER FREE DROP TEST 4

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(9)

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APPENDIX 2b DROP TEST ONTO CLOSURE END

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(13)

APPENDIX 3 (Con't)

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PUNCTURE TEST l

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l APPENDIX 4 l '~ '

i THERMAL l

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