ML20010A735

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Addl Testing of DT-14 Shipping Container
ML20010A735
Person / Time
Site: 07109852
Issue date: 06/30/1981
From: Crowden H
UNION CARBIDE CORP.
To:
Shared Package
ML20010A734 List:
References
19422, Y-LA-810, Y-LA-810-R01, Y-LA-810-R1, NUDOCS 8108120133
Download: ML20010A735 (19)
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Text

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a-l ADDITIONAL TESTING OF DT-14 UNION SHIPPING CONTAINER CARBIDE

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H. E. Crowder i

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June 1981 1

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8108120133 810721 PDR ADOCK 07109852 C

DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibihty for the accuracy, complete-ness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific com-mercial product, process, or service by trade name, trademark, i

manuf acturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect thost of the United States Government o any agency

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Date of issue: June 30,1981 Y/LA-810 Revision 1 ADDITIONAL TESTING OF DT-14 SHIPPING CONTAINER H. E. Crowder Container Engineering Department Product Engineering and Scheduling Division Oak Ridge Y-12 Plant P. O. Box Y, Oak Ridge, Tennessee 3 /830 Prepared for the Department of Energy Under Us Government Contract W-7405-eng-26

2 INTRODUCTION The data contained within documents additional testing of the DT-14 Fissile Material Shipping Container as requested by the Department of Energy and the Nuclear Regulatory Commission.

The intent of this report is to answer NRC's questions as referenced in Docket Number 71-9852. If this documentation is satisfactory to NRC, a revision to the Safety Analysis Report for Packaging will be required. With an approved revised S.A.R.P., the DT 14 package could be used throughout the entire nuclear industry.

Listed below are the questions as mentioned in Docket No. 71-9852 and Y-12's response.

STRUCTURAL Demonstrate that the integrity of flanged and bolted containment vessel,shown in Figure 3 of Report No. Y/DD-244, January 1978, maintains its integrity for a 30-foot bottom end drop with maximum content weight.

The inner containment vessel was loaded with 30 Kg's of simulated weight and blotter paper was attached to the inside surface of the lid before securing the bolts. The inner vessel was installed into the outer drum and secured for the 30-foot bottom end drop. (Ref. Figure 1).

An eyebolt was installed into the center of the drum lid for lif ting during drop test. (Ref.

Figure 2 ) The loaded container was dropped from 30 feet onto the bottom-end as shown in Figure 3. Slight damage was incurred on the bottom and lower roll ring with no breakthrough on the metal walls of the drum. The locking ring and botting mechanism received no damage and remained secure. (Ref. Figure 4 )

CONTAINMENT 1

1. Develop a containment criteria based on the dispersibility and radiotoxicity of the contents for normal conditions of transport and accident damage conditions. Regulatory Guide 7.4 may be used in establishing this criteria.
2. D onstrate that the containment vessels (shown in Figures 3 and 4 of Report N o.

'DD-244, January 1978) meet the established containment requirements for norm.

onditions of transport and accident damage conditions.

The inner containment vessel of the DT-14 Package is leaktight in accordance with ANS N14.5 para. 3.5 and does not require a containment criteria for the dispersibility and radiotoxicity of the contents for normal conditions of transport and accident damage conditions. Figure 5 documents the leaktightness before thermal testing. The inner i

containment vessels were water immersion tested 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter the thermal test by l

submerging each vessel in color-dyed water and externally pressurizing to 172 KPa (25 psig).

The seals of the vessels demonstrated the water tightness of the vessel for periods exceeding eight hours.

l STRUCTURAL TESTING FIGURE 1 The inner containment vessel was loaded with 30 kg of simulated weight, and blotter paper was attached to the bottom side of the lid before securing the bolts with 12 indlb of torque.

An eyebolt was installed on the lid of the outer drum to provide lifting capabilities for the 30 foot bottom-end drop test. The inner vessel was installed into the outer drum and secured for the 30 foot drop test.

FIGURE 2 i

This is a close-up view of the locking ring and bolt before the 30-foot drop test was performed.

FIGURE 3 The loaded container was dropped from a distance of 30 feet onto the bottom end of the container. Slight damage was incurred on the bottom chime and lower roll ring with no breakthrough on the metal walls of the drum.

FIGURE 4 The locking ring and bolting mechanism received no damage and remained secured.

INNER CONTAINMENT LEAK TESTING FIGURES 5 THROUGH 14 The DT-14 meets the leak rate requirement as referenced in Paragraph 3.7 of ANSI /N14.5 and does not require a containment criteria for dispersibility and radiotoxicity. Photographs of a step-by-step procedure were made to further demonstrate the ability of inner containers to meet requirements for normal conditions of transport and accident damage conditions.

The water submersion testing procedure is shown in item 2 of Figure 5; Figures 6,7,8, and 9, illustrate the testing.

No photographs were made of the Halogen Leak Test; however, no leakage was observed (see item 3, Figure 5).

The red dye submersion testing procedure is shown in item 4 of Figure 5; Figures 10, 11,12,13, and 14 illustrate the testing.

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4 FIGURES 15,16, AND 17 Af ter all tests were completed, the inner container was opened to inspect for internal leakage. The white blotter paper revealed no evidence of leakage.

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I TS-80F-819-083 NUCLILAR DIVISION ist! stas cassesHn rt u r August 19, 1980

/H. E. Crwder 9720-3, MS-1 (4-2689)

DT-14 Fissile Material Container, Drawing Nuct'er T2E-9,983, Rev. G This report certifies that one DT-14 container on the above drawing was tcsted in the following manner:

1.

Container lid was checked for a minimum of 12in./lb. torque per bolt before pressure was applied.

2.

Using nitrogen, a pressure of 7.5 psig was applied internally as e ANSI N-14.5 - 1977 (American National Standard for Leak.gv Tests on Packages for Shiprent of Radioactive Materials),

Appendix A-3.3, Soap Bubble. Pressure was held for 15 minutes, and all suspected leakage areas were coated with a liquid soap solution; no leakage was observed. While container was pres-surized at 7.5 psig internally, an additional test was applied by submerging container in water for 15 minutes; no leakage was observed at this point.

3.

A third test was then arnlied as per ANSI N-14.5 - 1977, Appendix A-2, Leakage Test Procedures, using spike nitrogen and pressurizing containers to 15 psig; halogen leak detector gun set at 10 2 through 107 rio leakage was observed.

4 A fourth test was applied to container. Container was submerged In red dye and pressurized externally to 25 psig and held for 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, as per H. E. Crowder. No leakage was observed.

W. T. Young, 9706-1A, MS-1 (4-2370)

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15 TESTING AND MAINTENANCE TESTING AND MAINTENANCE Establish a test and maintenance plan for the containment vess a in service. Regulatory Guide 7.4 may be used for periodic testing. For assembly verification, it is recommended '

that a test of sufficient sensitivity to limit the maximum release to a Type A quantity in 10 days is used, however, a leak test sensitivity greater than 1X10-3 at-cm3/sec, would not be required. The minimum sensitivity of 1X10-1 at-cm3 sec (air at 1 atm and 25 C leaking

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to a 10-2 at ambient) as specified in ANSI N14.5 should be met.

- A visual inspection of the DT-14 package is performed af ter each use to insure the container -

is functional and-that no damage has occurred from prior usage. After each. visual inspection, the Numbers 1,2, and 3, are placed on the lid of the inner vessel to indicate the number of visual inspections the vessel has received since the last leak test.

Leak. tests will be performed on the irr r vessel after its third use in accordance with Y-12's Standard Vacuum Leak Test Procedure 00-R-023, Rev. A. (Ref. Figure 18.) Records will be maintained on the inner containers latest leak test.

A container that fails to certify will be reworked and retcied before it is used for shipment.

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16 ASSEM BLY DIVISION UNION CARBIDE CORPORATION NUCLE AR Olvl5tO*e A

p OAK RIDGE Y 12 PL ANT STANDARD VACUUM LEAK TEST f

PROCEDURE Beta-4 Assembly 1.0 SCOPE This procedure describes the method for leak testing assemblies and/or parts using a mass spectrometer leak detector. The assembly will be evacuated and the assembly exterior exposed to a helium atmosphere.

2.0 GENERAL This standard vacuum leak test procedure will cover most applications of vacuum leak testing requiring lx10 7 or f x10 6 atm. cc/sec. range. Any differences resulting f rom design or Test requirements of an assembly or subassembly must be addressed in the assembly procedure for that unit.

3.0 EQUPIMENT 3.1 Leak Detector - Helium sensitive mass spectrometer 3.2 Valve Manifold 3.3 Helium supply 3.4 Standard leaks (certified) 2.4.1 Production standards <lxt0-6 2.4.2 Part standard

<lx10-7 3.5 Plastic bag 3.6 Auxillary vacuum pump (opp.)

4.0 LEAK DETECTOR SENSITIVITY OiECK 4.1 Close all valves to standard leaks and assemblies.

4.2 Put start-vent switch in start position and allow L.D. to pump down.

4.3 Adjust scale f actor switch to highest sensitivity setting and adjust sensitivity so that meter reads between 0 and 5% of scale.

PR OD. E NGR.

OPE R ATIONS DOCUMENTHO.

R E Y.

00-R-023 A

A M/rD l-pgf (5p

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d Figure 18. STANDARD VACUUM LE AK TEST PROCEDURE

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UNION CARBIDE CORPORATION NuCLI AR D6VIOON O

OAK RIDGE Y 12 PL ANT 4.0 LEAK DETECTOR SENSITIVITY CHECK (Con'.)

4.4 Open production standard and reset scale f actor switch to highest obtainable reading within meter limits. Note meter reading.

4.5 Open part standard and close production standard. Allow to stabillze.

Note meter reading.

4.6 Verify leak 1etector sensitivity once per shif t by calculating part standard i 25% using the following formula:

(Item 3.5 reading) b 0**

sPart Std. Re; ding) X (Scale Factor)

Certification Value of

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(Pro. Std. Read i ng) X (Scale Factor)

Production Standard 5.0 ASSEMBLY AND/OR PART LEAK TEST 5.1 Open production and part standards. Using L.D. and auxiliary pump (if available) evacuate assembly, manifold and included lines.

5.2 Cover assembly or section of assembly to be tested with a plastic bag:

(tape may be used to hold bag in place). Fill bsJ wiih bellum. To insure a helium atmosphere, a light purge of helium may be necessary during testing operation.

5.3 After pressure reaches se

'.and on micron gauge 15 microns and L.O.

s=liches to di f f usion pump, close valve to auxiliary vacuum pump and slowly open throttle valve (if closed) and turn filament on, aad close procution standard. Allow meter to stabilize.

5.4 Obsere meter reading (pbrt and part std. readirg) and then close part standard allowing meter to stabilize. Again, observe meter reading (part cnly reading). Using the following formula, calculate leak rate of part.

Leak Rate,

nr, Readin@ X (Scale Factor)

Certified Value of (Schie Factor)X (Part Std. kaadin') X Part Standard g

5.5 If leak rate is acceptable, close throttle valve, turn off filament and vent assemb ly.

t DOCUMENT No.

R E v.

00-R-023 A

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3 Figure 18. fcontinued)

7-t 18 ASSEMBLY DIVl510N l

UNION CARBIDE CORPORATION NUCL{A Yllio4 OAK RfDGE Y.12 PL ANT 5.0 EQUIPMENT DIAGRAM Discharge Throttle huge y,j,,

mter Part Std.

Manifold Sensitivity Adjustment

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Pact 3 or 3 Figure 18. (continued)

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