ML20127L438

Certificate of Compliance 9247,rev 0,model 11OG-A Package

ML20127L438
Person / Time
Site:	07109247
Issue date:	01/22/1993
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20127L420	List: ML20127L418 ML20127L438
References
NUDOCS 9301270151
Download: ML20127L438 (12)

Text

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' CERTIFICATE CF COMPLlANCE 1

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FOR RADIOACTIVE MATERIALS PACKAGES

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9247-0 USA /9247/A 1

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e. Thi. ceriiviceie i. i..u.o io ce,ia in.i ine p.ck.ging and content oe.crio d in eiem e beiow. meeis ine appuc.bie iee stanoaroe..t vorin in Tine io. coo. -

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r o# rederst Regu6stions, Part 71, *Peckaging eno Transportahon of Radsoectwo Materiot' l

I a Thre certificate does not reheve the consignor from compnence witn any reou4ement of the reguisuons of the u s. Departinent of Transporte: ion or otner apphceue rogue iory agenciet incevoing one government of any country inrouan or into wnict. ine peen.g. wui de iren.portoo.

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I 3 THIS C.uio io w m. if RTW4cATE 18 ISSUED ON THE DAttS OF A &Af ETY ANAtVS8$.Rf PORT OF THE cAcKAOE f>Ebl,ON 04 APreticATION ~

1 e is mte Ano ocmvicArou o seront on AmacAton I

Nuclear Fuel Services, Inc.

Nuclear Fuel Services, Inc. application 8

i P.O. Box 337, MS 123 dated July-31, 1992, as supplemented.

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Erwin, TN 37650

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I This cettif6cate is conddsonal upon fulfdl6ng tne requirement 6 of 10 CFR Part 71, es apphcable, and the conditions specified Delow l

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Model No.:

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Description 7'

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Concrete-filled,110-gallon drum for transport of wastes meeting the i

I requirements ~ of_ low specificiactivity radioactive material. The I

l package is composed ;of an.i_nner, DOT Lspecification 17H, 55-gallon l

t drum,. excluding lid,~ centered within an outer,-110-gallon' drum by y

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5,000 psi compressive strength concrete. After waste emplacement in -

I the inner drum, concrete is poured to fill the~ inner drum and to-I N

extend ~above the top chimesof the inner drum. The outer drum and lid I

I are 16-g' age. steel.

The outer drum is closed by a 12-gage steel I

l locking ring with drop _ forged lugs, a 3/8-inch smooth neoprene gasket, l

and a 5/8-inch diameter bolt., The maximum weight of the package, y

i including contents,;is 2700-pounds) i I

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-Drawings 1

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The packaging is constructed in accordance with Nuclear Fuel Services, l

inc. Drawing No. 000-M0034-B, Rev. B.

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CONDfTlONS (continued) l'!

Page-2'--Certificate No. 9247_- Revision No. 0 - Docket No. 71-9247 Y

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Contents t

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Type and form of material I

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i Dry, solid waste material meeting the requirements of-low specific I

activity radioactive material. The waste material.is in the form of

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l disks composed of super-compacted 40-gallon drums.containing non-r l

compactible or compacted wastes.

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Maximum quantity of material per package I

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Greater than Type A quantities of radioactive materials. The maximum I

weight of waste materialtis;1',000 pounds. The contents may include I

fissile materialsppFovided'thht ths, total quantity of. fissile

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l material pepg'ackage meets the mass 11mit specified in 10 CFR t-l 571.53(a.Q 1X f

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(a)

For any package containing water or organic substances' which could

[i radiolytically generate combustible gases, a determination m.ust be made by

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-tests and. measurements or by analysis of a-representative package that the t

l followingicriteria-aYe eet over a period'of; time that is twice the-expected

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shipment'-time:

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$N I-The hydrogen generat'edimus)t behimitekt'ofa ' molar quantity trat wo

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more than'5% by,vol6mel(oraquivalent-1.imits for other?inflanmable gases) of the package gas tvoid'ifspresent at STPT 1Ve., no more than 0.065 g-moles /ft l

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For any package" delivered;to taj carrjer for.tran' sport,"the package must be r

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s generation 0smade.)Shipmentiperiodsbegins;whenthepackageisprepared.

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(sealed) and niust be comp'leted.within"twic~e the expected shipment time.

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For any package (shipped within 10 days after sealing of the drum, the i

I determination in '(a) above need not be made, and the time restrictio'n in (a) [

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Radioactivity per package shall be determined in accordance with Sections 1.2.4 r

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In addition to the -requirements of Subpart G of 10 CFR Part 71, the package _shall

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l be prepared fer-shipment and operated 'in accordance.with ~Section 4 of the j

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This certificate authorizes land transport between the vicinities of Oak Ridge, I

I Tennessee, and Barnwell, South Carolina, only.

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The package authorized by this certificate must be transported on a motor vehicle t

I or railroad car' assigned for sole use of the licensee.

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.Page Certificate No. 9247 - Revision'No. 0 Docket No. 71-9247 I

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The package authorized by this certificate is hereby approved for use under the i

general license provisions of 10 CFR 671.12.

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Expiration date: January-31, 1998.

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l BEFERENCES l

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Nuclear Fuel Services, Inc. application dated July 31, 1992.

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Supplement dated:

November 25, 1992.

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SAFETY EVAL.UATION REPORT Model No.110G-A Package Certificate of Compliance No. 9247 Revision No. O

SUMMARY

By application dated April 22, 1992, as supplemented July 31, 1992, and November 25, 1992, Nuclear Fuel Services, Inc. (NFS) requested approval of the Model No. Il0G-A package as a transport package for greater than a Type A quantity of low specific activity radioactive material.

Based upon the statements and representations contained in the application, as supplemented, and the conditions listed below, we have concluded that the Model No.110G-A package meets the requirements of 10 CFR Part 71.

REFERENCES Nuclear Fuel Services, Inc. application dated July 31, 1992.

Suppicment dated November 25, 1992.

DESCRIPTION Concrete-filled,110-gallon drum for transport of wastes meeting the requirements of low specific activity radioactive material. The package is composed of an inner, 00T specification 17H, 55-gallon drum, excluding lid, centered within an outer,110-gallon drum by 5,000 psi compressive strength concrete. After waste emplacement in the inner drum, concrete is poured to fill the inner drum and to extend above the top chime of the inner drum..The outer drum and lid are 16-gage steel. The outer drum is closed by a 12-gage steel locking ring with Jrop forged lugs, a 3/8-inch smooth neoprene gasket, and a 5/8-inch diameter bolt. The maximum weight of the package, including contents, is 2700 pounds.

DRAWINGS The packaging is constructed in accordance with Nuclear Fuel Services, Inc.

Drawing No. 000-M0034-B, Rev. B.

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110 GALLON OUTER LDRUM 55 GAL. DRUM DDT 17H

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MODEL N0. 110G-A PACKAGE-4 l

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3 CONTENTS A.

Type and form of material Dry, solid waste material meeting the requirements of _ low specific activity radioactive material.

The waste material is in the form of disks composed of super-compacted 40-gallon drums containing non-compactible or compacted wastes.

B.

Maximum quantity of. material per package Greater than Type A quantitles of radioactive materials. The maximum weight of waste material is 1,000 pounds.

The contents may include fissile materials,~ provided that the total quantity of fissile material per package meets the mass limit specified in 10-CFR 571.53(a).

STRUCTURAL EVALUATION The contents of the package consist of dry solid waste material of low specific activity.

Consequently, the structural evaluation of the package design showed that the design meets the requirements of 10 CFR Part 71 for-normal conditions of transport.

A.

General Standards for All Packaaes Minimum oackace size No dimension of the package is less than four inches.

The package meets the requirements of 10 CFR s71.43(a) for minimum size.

Tamper-proof feature Each drum closure is equipped with a conventional wire seal which passes between the locking ring bolt loops. Opening of the drum is not possible without destroying the integrity of this seal.

An intact seal is evidence that the package has not been opened by unauthorized persons.

Positive closure The closure mechanism consists-of a conventional locking ring and_

threaded-bolt closure which cannot be opened inadvertently.

Chemical and calvanic reactions There are no materials of construction within the package which will create significant chemical, galvanic, or other reactions among the packaging components, or between the packaging components and package contents.

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Valves or other devices There are no valves or other devices on the package.

B.

Liftina and Tie-down Standards for All Packaaes Liftina devicgi No attachments will be made which form a structural part of the package and which could be used as lifting devices.

Lifting and transfer of_ the packages will be by positioning the packcges on wooden pallets and using a forklift.

Tie-down devices There are no devices that are a structural part of the package which might be used as tie-downs. Tie-down and securing of packages to preclude shifting within the transport vehicle will be by construction of conventional wooden shoring as needed along sides, top, and ends of the load, and along outer bottom edges of the rows of drums.

C.

Normal Conditions of Transport Heat There will be no significant stress increase in the package under the.

normal transport heat condition.

[91d The package was exposed to a low temperature environment of--40'F for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The package showed no evidence of: adverse effects as a result.of exposure to low temperature.

Reduced external oressure and increased external oressure The reduced and increased pressure tests were performed six-times, each time with a different configuration - twice with different gasket materials, once with a new closure ring, once on an empty drum and t

finally with the drum closure' configuration as specified on.the packaging drawing.

A vacuum pump was used to simulate an increased external pressure of 20 psia by establishing a vacuum inside the drum'of 5.3 psi differential pressure. Compressed air was introduced into the drum to simulate a decreased external pressure of 3.5 psia by pressurizing the inside of the drum to 11.2 psig.

In all the tests there was no damage to the drum, however, the drum failed to maintain -

the 11.2 psig internal pressure.

A reduced external pressure test was then performed to simulate the elevations anticipated for the. transit from Oak Ridge,- Tennessee, to Barnwell, South Carolina (less than 6,000 feet).

The initial 4.7 psig internal pressure was held constant at 4.3 psig (equivalent to 7,600 feet elevation) for 10 minutes.

Because the

P b contentsiare totally encapsulated in concrete, the-staffiagrees;that the reduced external pressure; test-is; adequate to assure-the: safety of-the shipment for elevations less than;-6,000 feet. The Certificate:of-Compliance includes a condition to limit the use of the Model No.110G-A-package for land shiomen s b1 tween Oak Ridge, Tennessee, Land Barnwell.

- South Carolina, only.-

Shock and vibration There are no valves or other devices on the. cont'ainer that-are susceptible to ' shock and vibration loads. - The radioactive contents are encapsulated in concrete. :There will be no significant--adverse = effects:

on the package from the shock and vibration loads normally incident to transport. '

Water soray-A package specimen was subjected to a water spray environment simulating two inches of rainfall'per hour. There was no_ evidence of inleakage of.

water into.the package, nor was.there any evidence that the. exposure _to; water would degrade the ability _ of the package to meetLany of: the other test requirements.

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free dron The package specimen containing the inner drum and concrete was cooled to -20*F and-' dropped onto a horizontal unyielding surface-from-a- height -

of four feet-onto-its top edge and then again dropped -from four-feet?

onto its cylindrical l side. -The locking ring 'and_ top lid'were-dented inward as a result of the drop onto the top edge, Land there was no evidence of leakage. -As a result of the' horizontal. side drop, the' top c

lid and ring clamp separated from the top _of-thefpackage. This failure was observed to beLcaused by the deformation in the c1os'ure ring: caused by the-top edge drop. A horizontal drop. test using'a new closure;ringc resulted in no separation of the drum lid.;

Two additional tests were performed to. verify _that-dropping the drumL directly on the closure ring' lug would'not cause failure. Two test-specimens. cooled to -20*F were dropped fromfa: height af four feet, one at 45' directly onto the closure ring lug-and the other flat on.the side-l -

with the closure ring lug oriented toward the! impact.: Although the outer drum, the: closure ring and the lugs were dented, there was noL

- exposed concrete nor release of material; Corner droo This test was not applicable because the _ weight of-the package exceeds-

- 220-pounds and_neither wood nor fiber board is used as a material of-construction.

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A continuous compressive load of 13,550 pounds (approximately-five times the package weight) was applied to the top of the package for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Inspection of the package revealed no anomalies or leakage of contents.

Thus, the package passed the compression test.

' Penetration A 1-1/4-inch diameter steel rod cylinder w'th a hemispherical end, weighing 13 pounds was dropped over a distance of 40 inches, through a.

steel guide tube sleeve, such that the hemispherical end of the rod struck perpendicular to the top, bottom and sides of the package. Three strikes were performed on each of the three surfaces..There was no evidence of leakage, loss of contents or other anomalies.

D.

Conclusion The package has been tested and assessed against the applicable-requirements of 10 CFR Part 71.

The tests were conducted at Wyle Laboratories in-iuntsville, Alabama. Based on the results of this testing and evalcation, it is' concluded that the package, excluding the reduced external-aressure, meets the performance criteria in 10 CFR Part 71..

A condit ion has been ir.cluded in the. Certificate of Compliance to assure safety o' the package under the reduced external pressure condition of transport.

THERMAL The maximum decay heat per package is approximately 1.5 milliwatt.

This decay heat is negligible.

CONTAINMENT The conu inment system is-defined as the outer 110-gallon drum. The drum is closed by a 12-gage locking ring and a 3/8-inch smooth neoprene gasket. The locking ving is secured by a 5/8-ll-UNC. ANSI Bl.1 Grade 2A bolt, torqued to 50 1 5 ft-lbs.

Testing of the package indicated that the 110-gallon drum was not capable of maintaining a seal under conditions of reduced external pressure.

However, %

L the applicant showed that the drum would maintain a seal under the reduced external pressure conditions which are expected during transport from Oak Ridge, Tennessee, to Barlwell, South Carolina. The maximum elevation to be traversed is 6,000. feet. Therefore the package was evaluated for a l

differential. pressure equivalent to a reduced external pressure of approximately 10 psia.

Use of the package ~ is authorized for. land transport' l

between Oak Ridge, Tennessee, and Barnwell, South Carolina, only.

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EVALUATION OF RADI0 ACTIVE CONTENTSL

- The radioactive material is in the form of contaminated! dry' waste generatedz from decommissioning activities. Compactible waste and non-compactible wastes; are packaged in 40-gallon drums. The 40-gallon drums are then _ super-compacted into disks.- The disks.are placed into the inner, 55-gallon drum, which is-centered within-the' outer 110-gallon drum by' concrete. Concrete isipoured,to fill the inner drum and to extend above the topfof;the inner drum; The radioactivity in the package meets the concentration requirementsLof low?

specific activity material, as defined in110 CFR 671.4. Only the weight ofL the disks is considcred when determining the specific-activity of.the: waste:

(the weight of the concrete is neglected).

The isotopic distribution is determined through analysis of smear samples. 'The radioactivity per package -

is determined by passive / active: neutron assay _ methods. The radioactivity-present per package,' assuming maximum concentration and the maximum mass of.

waste (1000 pounds), was estimated as follows:

Radionuclide Curies-Uranium-233 1.73E-3 Uranium-234 1.82E-4 Uranium-235 2.32E-6 Uranium-238 1.30E-5 Plutonium-238 7.20E-3 Plutonium-239 1.48E-2 Plutonium-240 6.20E-3 Plutonium-241 8.34E-2 Plutonium-242 3.24E-6 Americium-241 1.48E-2 TOTAL 1.28E SHIELDING The radioactive materials to be shipped do not present a-direct radiation ~

hazard. The concrete in-the package-is present for waste stabilization, and is not necessarily needed for shielding: purposes.

The' applicant stated that.

the dose rates from loaded. packages could. range'from 0.1-to 10_ millirem / hour at the package surface ~and from 0.1 to 1.5 millirem / hour:at one. meter:from the -

package.- These dose-rates meet the external radiation standards of 10 CFR-

$71.47. The operating procedures for the package specify that radiation-measurements be taken-for each package ~ prior to shipment.

CRITICALITY

- The package contains fissile materials. However, the maximum mass of fissile material per package is limited to the exempt quantity tus specified:in 10 CFR

$71.53(a). Therefore, criticality is not a concern.

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• FABRICATION Materials of construction are specified on the packaging drawing. The inner drum is a 55-gallon DOT specification 17H drum.

The outer drum is a 110-gallon drum of 16 gage steel.

Every four months a randomly selected 110-gallon drum is hydrostatically tested. The concrete is high-compressive strength (5,000 psi) ASTM 3-143 concrete.

Prior to waste emplacement, the packaging is inspected to assure that it is properly fabricated, and that all components are present and undamaged.

OPERATING PROCEDURES AND ACCEPTANCE TESTS The applicW ; 'ovided acceptance tests in Section 4.7 of the application.

The acceptance tests include visual inspection of all components, marking of the package, and inspection of the gasket and sealing surfaces.

The applicant provided procedures for loading the package and preparing the package for shipment in Section 4.8 of the application.

The procedures include: verification that the contents are proper for the package, j

emplacement of the waste, pouring of the concrete plug, and installation of the drum closure. The procedures specify pre-shipment radiation and contamiriation surveys, and the application of a tamper-proof seal.

Maintenance procedures were not provided since this is a single use container for waste disposal.

CONDITIONS 1.

(a)

For any package containing water or organic substances which could radiolytically generate combustible gases, a determination murt be made by tests and measurements or by analysis of a representative package that the following criteria are met over a period of time that is twice the expected shipment time:

The hydrogen generated must be limited to a molar quantity that would be no more than 5% by volume (or equivalent limits for other inflammable gases) of the package gag void if present at STP (i.e., no more than 0.065 g-moles /f t at 14.7 psia and 70 'F).

For any package delivered to a carri<r for transport, the package must be prepared for shipment in the m e manner in which determination for gas generation is made.

Shipment period begins when the package is prepared (sealed) and must be completed within twice the expected shipment time.

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(b)

For any package shipped within 10 days after sealing of the drum, the determination in (a) above-need not be made, and the time restriction in (a) above does not apply.

2.

Radioactivity per package shall be determined in accordance with Sections 1.2.4 and 4.8 of the application.

3.

In addition to the requirements of Subpart G of 10 CFR Part 71, the package shall be prepared for shipment and operated in accordance with Section 4 of the application.

4.

This certificate authorizes land transport between the vicinities of Oak Ridge, Tennessee, and Barnwell, South Carolina, only.

5.

The package authorized by this certificate must be transported on a motor vehicle or railroad car assigned fer sole use of the licensee.

CONCLUSIONS Based on the review of the statements and representations contained in the application and'the conditions listed above, we have concluded that the Model No. Il0G-A package meets the requirements of 10 CFR Part 71.

MJ0 Charles E. MacDonald, Chief Transportation Branch Division rJ Safeguards'and Transportation, NMSS Date