ML20057B219

Certificate of Compliance 9254,Rev 0,for Model 40G-A

ML20057B219
Person / Time
Site:	07109254
Issue date:	09/15/1993
From:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20057B216	List: ML20057B215 ML20057B219
References
NUDOCS 9309200172
Download: ML20057B219 (10)

Text

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l U.S. NUCLEAR REcULATORY COMMISSI~N Nac Fons ets' CERTIFICATE OF COMPLIANCE I

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So cm" FOR RADIOACTIVE MATERIALS PACKAGES I

i e ctRTIDCATE NUMBER D REVISION NUMBER c PACKAGE IDENT1hCAT!ON NUMBER d.PAGE NUMBER

e. TOTAL NUMBER PAGES 9254 0

USA /9254/A 1

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a. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the apphCable safety standards set forth in Title 10, Code

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of Federal Regulations. Part 71. " Packaging and Transportation of Radioact.ve Matenal."

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J b inis cer..ficate does noi reheve ine consignor trom comphance witn any requeement of ine reguistions of tne u.s oepanment of Transportation or otner J

apphcabie regulatory agencies. including the government of any country through or into which ine package wiii be transported.

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a; Nuclear Fuel Services, Inc.

Nuclear Fuel Services, Inc.,

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P.O. Box 337, MS 123 application dated July 2, 1993.

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Erwin, TN 37650 fI 1

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c.oocxtrNuussR 9254

4. CONDirlONS d

This certificate is conditional upon fulfilbng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified below.

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1 (a)

Packaging i

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(1)

Model No.: 40G-A 1

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Description p

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Packaging for transport of wastes meeting the requirements of low specific E

i activity radioactive material. The packaging consists; of a 40-gallon, l

I 20-gaugeEcarbon steel, open-head. drum.- The drum is closed by a 20-gauge, f

j carbon steel lid; a 3/8-inch, half-round tubular, smooth, black neoprene g

gasket; a 12-gauge, ~ forged steel, closure ring; and a~ 5/8-inch diameter bolt.

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i The dimensions of the packaging are-36 inches high by 18-1/4 inches outer E

1 diameter. The maximum weight of the package, including contents, is L

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333 pounds.

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(3)

Drawings

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

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Drawing No. 000-M0075-B, Revision A.

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j (b) Contents 1

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(1)

Type and form of material L

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1 Dry, solid waste material meeting the requirements of low specific activity I:

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radioactive material. The waste material is in the form of non-compactible i

1 materials and compacted bales, approximately 16 inches by 16 inches and 2 to

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j 10 inches thick. The material shall have no sharp points, edges, or corners t

i and shall be triple-wrapped in plastic.

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1 (2)

Maximum quantity of material per package 1

1 Greater than Type A quantities of radioactive materials. The maximum weight

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of the waste material is 300 pounds. The contents may include fissile

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material provided that the total quantity of fissile material per package it 1

meets the mass limit specified in 10 CFR 671.53(a).

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m_m CONolTIONS (continued)

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Page 2 - Certificate No. 9254 - Revision No. 0 - Docket No. 71-9254

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(a)

For any package containing water or organic substance which could radiolytically generate combustible gases, a determination must be made, by

l tests and measurements or by analysis of a representative package, that the

!y following criteria are met over a period of time that is twice the expected lp shipment time:

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W The hydrogen generated must be limited to a molar quantity that would be no l8 more than 5% by volume (or equivalent limits for other inflammable gases) of j!g the package gas void if present at STP (i.e., no more than 0.055 g-moles /ft at 14.7 psia and 70 'F).

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i For any package delivered to a carrier for transport, the package must be jl L;

prepared for shipment in the same manner in which the determination for gas generation is made. The shipment period begins when the package is prepared 5lj d

(sealed) and must be completed within twice the expected shipment time.

g (b)

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

j determination in (a) above need not be made, and the time restriction in (a) iN p

above does not apply.

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Radioactivity per package shall be determined in accordance with Sections 1.2.4 and p

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4.8 of the application.

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8.

In addition to the requirements of Subpart G'of 10 CFR Part 71, the package shall I

be prepared for shipment and operated in accordance with Section 4 of the j

application.

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9.

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

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or railroad car assigned for sole use of the licensee.

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10.

The package authorized by this certificate is hereby approved for use under the general license provision of 10 CFR 671.12.

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11.

Expiration date: September 30, 1998.

j REFERENCES

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Nuclear Fuel Services, Inc., application dated July 2,1993.

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)l5 FOR THE U.S. NUCLEAR REGULATORY COMMISSION E

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.e Cass R. Chappell, Se'ction Leader l)y Cask Certification Section Storage and Transport Systems Branch B

Division of Industrial and

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j' Medical Nuclear Safety, NMSS SEP 15 1993

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E UNITED STATES lI y

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 2055H001

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SAFETY EVALUATION REPORT Model No. 40G-A Certificate of Compliance No. 9254 i

Revision 0 j

SUMMARY

By application dated February 3, 1993, Nuclear Fuel Services, Inc. (NFS),

requested approval of the Model No. 40G-A package as a transport package for greater than a Type A quantity of low specific activity radioactive material.

On July 2,1993, NFS submitted a revised application which completely supersedes the February 3, 1993, submittal.

Based on the statements and representations in the application and the conditions listed below, we have concluded that the Model No. 40G-A package meets the requirements of 10 CFR Part 71.

REFERENCES Nuclear Fuel Services, Inc., application dated July 2,1993.

DESCRIPTION Packaging for transport of wastes meeting the requirements of low specific activity radioactive material.

The packaging consists of a 40-gallon, 20-gauge, carbon steel, open-head drum. The drum is closed by a 20-gauge, carbon steel lid; a 3/8-inch, half-round tubular, smooth, black neoprene gasket; a 12-gauge, forged steel, closure ring; and a 5/8-inch diameter bolt.

The dimensions of the packaging are 36 inches high by 18-1/4 inches outer diameter. The maximum weight of the package, including contents, is 333 pounds.

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

Drawing No. 000-M0075-B, Revision A.

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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 non-compactible materials and compacted bales, approximately 16 inches by 16 inches and 2 to 10 inches thick.

The material shall have no sharp points, edges, or corners and shall be triple-wrapped in plastic.

B.

Maximum Quantity of Material per Package Greater than Type A quantities of radioactive materials.

The maximum weight of the waste material is 300 pounds.

The contents may include fissile material provided that the total quantity of fissile material per package meets the mass limit specified in 10 CFR G71.53(a).

Model No. 40G-A Package 8

OREATEST Outs!0E DIMEN$tCN g,.8 K" y

FORCED LUG RING FOR 18%"

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BLACK T OPRENE Gasket 9

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OUTSIDE OtAMETER.

STRUCTURAL EVALUATION The content of the package consists of dry, solid waste material of low specific activity. The structural evaluation shows that the package design 1

meets the requirements of 10 CFR Part 71 for normal conditions of transport.

A.

General Standards for All Packages Minimum Packaae Size No package dimension is less than 10 centimeters (4 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 the drum is not possible without destroying the integrity of this seal.

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

Positive Closurt The closure mectanism consists of a conventional locking ring and threaded bolt closure Knich cannot be opened inadvertently.

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

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

B.

Lifting and Tie-Down Standards for All Packaaes liftina Devices i

No attachments will be made which form a structural part of the package and which could be used as lifting devices. The packages will be lifted i

and transferred by palletizing on wooden pallets, by using a fork truck and drum lifting attachments on the vehicle forks that grip the sides of the package, or by using lift slings that grip the top of the package.

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 L

• conventional wooden shoring as needed along the sides, top, and ends of the load, and along the outer bottom edges of the rows of packages.

C.

Normal Conditions of Transport Heat The package contents have negligible decay heat. There will be no significant stress increase in the package under the normal transport heat condition.

Cold 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 />.

Exposure to low temperature did not adversely affect the package.

Reduced External Pressure and Increased External Pressure To simulate an increased external pressure of 20 psia, a vacuum pump was used to establish 8.7 psi vacuum inside the drum. To simulate a decreased external pressure of 3.5 psia, compressed air was introduced into the drum to pressurize the interior to 11.2 psig. The reduced and increased pressure tests were performed three times. The two initial tests failed because of inadequate locking rings. The first test was run using lever latch locking rings which did not provide adequate closure. On the second test, the bolted locking ring used was for a larger diameter drum and did not provide adequate closure. On the third test, with proper locking rings, the drum contained the pressure differentials for ten minutes.

Shock and Vibration There are no valves or other devices on the drum that are susceptible to shock and vibration loads. Also, a specimen package was placed on a vibration table and vibrated at a frequency of 182 rpm for an hour. No anomalies or loss of contents were detected.

Water Spray A specimen package was subjected to a water spray environment simulating i

two inches of rainfall per hour. There was no evidence of water leakage into the package, nor was there any evidence that the exposure to water would degrade the ability of the package to meet any of the other test requirements.

Free Drop The package specimen was pre-conditioned to -20*F and dropped onto a i

horizontal unyielding surface, from a height of four feet and at an angle of 45*, onto its top edge. The package specimen was again dropped from four feet high squarely from the horizontal onto its cylindrical side.

The edge was dented from the edge drop but no loss of contents was noted..

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A second drop test was conducted to verify that dropping the package onto the locking ring lug would not cause failure. The drums were packaged with non-radioactive bales.

Sand was added as an indicator of loss of contents during the drop. The edge and side of the package was dented but there was no loss of contents or structural integrity.

A third drop test was conducted to determine if the sand in the second test could act to cushion the contents and thereby invalidate the second drop test.

Two test drums were packaged with non-radioactive bales and scrap metal for a total package weight of 340 and 351 pounds. The bales were oriented in the drum parallel to the impact surface to provide the most severe potential for damage. The test specimens were pre-conditioned to -20' F and dropped onto a horizontal unyielding surface, from a height of four feet and at an angle of 45*, onto the locking ring lug. The second package was dropped from four feet high squarely from the horizontal onto its cylindrical side with the locking ring lug oriented downward.

The edge and side were dented from the drops but there was no loss of contents or structural integrity of the packages.

Corner Drop This test is not applicable because the weight of the package exceeds 200 pounds and neither wood nor fiberboard is used as a material of construction.

i Compression A continuous compressive load of 1,400 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 j

A 13-pound, 1-1/4-inch diameter, steel rod with a hemispherical end was dropped over a distance of 40 inches, through a steel guide tube, 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.

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D.

Conclusion j

The package has been tested and assessed against the applicable

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requirements of 10 CFR Part 71. The tests were conducted at Wyle Laboratories in Huntsville, Alabama.

Based on the results of the tests 1

and the evaluation, it is concluded that the package meets the performance criteria in 10 CFR Part 71.

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THERMAL i

The package contents have negligible decay heat.

CONTAINMENT The containment system is the 40-gallon, 20-gauge carbon steel drum. The drum is closed by a 20-gauge, steel lid; a 3/8-inch, half-round tubular, smooth, black neoprene gasket; and a 12-gauge, forged steel closure ring.

The ring is secured by a 5/8-inch bolt which is torqued to 40 1 4 ft-lbs.

Package testing was used to show that the containment system remained sealed and retained the radioactive contents under normal conditions of transport.

EVALUATION OF RADI0 ACTIVE CONTENTS The radioactive material is in the form of contaminated dry waste generated from decommissioning activities.

The dry wastes may consist of compacted metal bales and non-compactible materials.

Items are wrapped in plastic sheets and heat sealed.

Radioactive contents are determined by sampling the contamination present in contaminated items on a batch basis. The fissile contents of the package are determined by passive / active neutron assay methods.

The maximum radioactivity per package is shown below. This radioactivity is based on a maximum content weight of 300 pounds, and the maximum concentration which maets the l

requirements for low specific activity radioactive material.

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Radionuclide mci /oka i

a Uranium-233 5.17E-1 Uranium-234 5.44E-2 Uranium-235 6.94E-4 Uranium-238 3.88E-3 Plutonium-238 2.16E+0 Plutonium-239 4.43E+0 Plutonium-240 1.86E+0 Plutonium-241 2.50E+1 Plutonium-242 9.70E-4 Americium-241 4.43E+0 TOTAL 3.84E+1 i

I The performance of the containment provided by the drum could be affected by the form of the waste materials.

The authorized contents are limited to materials similar to the materials tested and described in the application.

The waste materials used in the testing program were non-radioactive metal

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-t bales which had been prepared by peening over any sharp points and triple-wrapping with plastic according to normal operating procedures. The Certificate of Compliance requires the bales to have no sharp points, edges, or corners and to be triple-wrapped in plastic.

SHIELDING The types of radioactive materials in the package do not present a direct radiation hazard; therefore, no shielding is needed. The typical range of radiation levels from the drums is 0.1-0.5 millirem /hr at the package surface, and 0.01-0.05 millirem /hr at one meter from the package. These dose rates meet the external radiation standards of 10 CFR 971.47. The shipping checklist used for the package specifies that radiation measurements be taken for each package prior to shipment.

CRITICALITY The fiss',le materials in the package do not exceed the exempt quantities defined in 10 CFR s71.53.

Criticality during transport is not a concern.

ACCEPTANCE TESTS AND OPERATING PROCEDURES Section 4.7 of the application contains the acceptance tests for the package.

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

Section 4.8 of the application contains the procedures for loading the package and preparing the package for shipment. The procedures include: verification that the contents are proper for the package, emplacement of wastes, and installation of the drum closure. The procedures specify pre-shipment radiation and contamination 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

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1.

(a) for any package containing water or organic substance which could radiolytically generate combustible gases,, a determination must be made, by tests and measurements or by analysis of a representative package, that the following criteria are met over a period of time J

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 )

-i inflammable gases) of the pacpage gas void if present at STP (i.e:,

no more than 0.065 g-moles /ft at 14.7 psia and 70 *F).

l For any package delivered to a carrier for transport, the package must be prepared for shipment in the same manner in which the determination for gas generation is made. The shipment period begins when the package is prepared (sealed) and must be completed within twice the expected shipment time.

(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.

The package authorized by this certificate must be transported on a motor vehicle or railroad car assigned for 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. 40G-A package meets the requirements of 10 CFR Part 71.

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Cass R. Chappell, Se on Leader Cask Certification Section Storage and Transport Systems Branch Division of Industrial and Medical Nuclear Safety, NMSS Date:

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