ML19344D758

Application for Renewal of Certificate of Compliance 9039 for Model 715

ML19344D758
Person / Time
Site:	07109039
Issue date:	04/11/1980
From:	TECH/OPS, INC. (FORMERLY TECHNICAL OPERATIONS, INC.)
To:
Shared Package
ML19344D757	List: ML19344D756 ML19344D758
References
16032, NUDOCS 8004280133
Download: ML19344D758 (34)

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i-PACKAGE DESCRIPTION TECHNICAL OPERATIONS

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MODEL 715

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Tech / Ops Rad.at on Products Dmson 40 Nortn Avenue Burbngton, Massachusetts 01803 Telephone (617) 272 2000 11 April 1980 Mr. Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. MacDonald:

We request renewal of USNRC Certificate of Compliance No. 9039 issued for Technical Operations Model 715 Type B Package. In accordance with your letter of 17 March 1980, eight copies of a consolidated application for this package are enclosed. In accordance with 10CFR170.31 Item 11.E, we are also enclos-7 ing e check for $150 for the renewal fee.

We are simultaneously applying to the U.S. Department of Transportation for an International Atomic Energy Agency Certificate of Competent Authority issued under the 1973 Revised Edition of IAEA Safety Series No. 6 for Type B(U) packaging.

We trust that this application satisfies your requirements for renewal of this certificate.

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'JfhnJ.MunroIII sTechnical Director JJM/fb xc:

R. R. Rawl, USDOT Encis.

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Radiation Products Division 40 North Avenue Burkngton, Massachusetts 01803 Telephone (617) 272-2000 11 April 1980 Mr. Richard R. Rawl Health Physicist Office of Hazardous Materials Regulation Materials Transportation Bureau Research and Special Programs Administration U. S. Department of Transportation Washington, DC 20590

Dear Mr. Rawl:

We request issuance of an International Atomic Energy Agency Certificate of Competent Authority for Type B(U) packaging under the 1973 Revised Edition of IAEA Safety Series No. f for Technical Operations Model 715 Type B package,

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USA /9039/B. We are requesting this certificate due to the serious difficulties we have encountered in transporting this package internationally with its approval based on the 1967 Edition of IAEA Safety Series No. 6.

We are enclosing two complete copies of the safety analysis report for this package. We are simultaneously applying to the U.S. Nuclear Regulatory Commission for renewal of USNRC Certificate of Compliance No. 9039 issued for this package.

We trust that this request contains the information you require for your review. Your prompt action would be greatly appreciated.

'ncere John J. Munro II Te anical'birector JJM/fb Encis.

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C. E. MacDonald, USNRC l

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Tech /Op3 Ra$ation Products Dmson 40 North Avenue Burhngton, Mass-ahusetts 01803 Telephone (617;. 4 2000 11 April 1980 P

Mr. John J. McLellan, P. Eng.

Associate Scientific Adviser Radioisotope and Transportation Division Atomic Energy Control Board P.O. Box 1046 Ottawa, CANADA KIP SS9

Dear Mr. McLellan:

We request renewal of Canadian Endorsement E22 for USA Type B Package Design Certificate USA /9039/B issued for Technical Operations Model 715 Type B Package. We have applied to the USNRC and USDOT for r.newal of the domestic f

and IAEA certificates for this package.

We are enclosing a copy of the safety analysis report for this package.

We will forward copies of the USNRC and IAEA Certificates as they are received.

We trust that this application includes the information required for re-newal of this endorsement. Please contact us if we can provide any additional information.

Sincerely 1

Jo n J. Mudro III Technical Director v

JJM/fb Encis.

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Tcch / Ops Ra$ation Products Dvison 40 North Avenue Burhngton, Massachusetts 01803 Telephone (617) 272-2000 F

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PACKAGE DESCRIPTION TECHNICAL OPERATIONS MODEL 715 l

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General Information 1.1 Introduction The Tech / Ops Model 715 shipping container is designed for use as Type B packaging for the transport of Tech / Ops Models 533, 616, 644 and 713 gamma ray projectors containing Iridium-192 as special form sealed radioactive sources. The Model 715 conforms to the criteria for Type B packaging in accordance with 10CFR71 and satisfies the criteria for Type B(U) packaging in accordance with IAEA Safety Series No. 6, 1973 edition.

1.2 Package Description l

1.2.1 Packaging The Model 715 shipping container consists of an outer steel drum t

with inside dimensions of 15.38 inches (391mm) diameter and 23.88 inches (606mm) high. The steel drum is fabricated from 18 gage (0.048 inch, 1.2mm thick) steel, MS 27683-2. The gross weight of the package with a Model 616 gamma ray projector is 105 lbs.

(47.7kg); with the Model 644, 102 lbs. (46.3kg); and with a Model 533 or 713,103 lbs. (4 5.8kg).

The steel drum is closed by means of a cover secured by a clamp

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ring head closure. The head closure is fastened by means of a bolt drilled for a seal wire to provide a tamper proof seal.

The steel drum is lined with high temperature insulation, MIL-I-2781 or FEL-I-2819, on the sides and ends. The minimum thickness of in-sulation is 1 inches.

Inside the insulation liner is a molded rubberized hair filler.

This filler is molded to conform to the configuration of the gamma ray projector to be transported. A separate molded filler is employed for each model projector to be shipped.

The radioactive source assembly is contained inside the gamma ray projector. The radioactive material is sealed inside'a stainless l

steel source capsule. The capsule acts as the containment vessel for the radioactive material. The gamma ray projector provides shielding for the radioactive source and also provides a means of securing the radioactive source in its proper storage position.

Descriptions of the Models 533, 616, 644 and 713 are provided in Section 1.3.

1.2.2 Operational Features The gamma ray projector is installed in the Model 715 shipping

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container using the proper molded filler for the gamma ray projector l

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to be shipped. The top plate of the molded filler is set in place over the projector. The top section of the insulation is then set in place. The container top is covered with the lid. The clamp ring is then placed around the lid and the bolt is tightened. A seal wire is inserted through the bolt and nut to provide a tamper proof seal.

1.2.3 Contents of Package The Model 715 is designed to be a shipping container for the Tech / Ops

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Models 533, 616, 644 and 713 gamma ray projectors. The maximum radio-active contents would be 240 curies of Iridium-192 as special form, y

Source Model No. 58101, in conjunction with the Models 616, or 120 curies of Iridium-192 as special form, Source Model Nos. A424-1, A424-9 and 58101 in conjunction with the Models 533, 713 and 644 3

respectively. These source assemblies satisfy the criteria for special form radioactive material in accordance with 10CFR71 and IAEA Safety Series No. 6, 1973 Edition (Section 2.8).

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t 1.3 Appendix 1.3.1 Descriptive Assembly Drawing, Model 715 t

1.3.2 Description of Tech / Ops Model 533 and 713 Gamma Ray Projector 1.3.3 Description of Tech / Ops Model 616 Gamma Ray Projector 1.3.4 Description of Tech / Ops Model 644 Gamma Ray Projector

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1.3.5 USNRC Certificate of Compliance USA /9039/B t

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1.3.1 D2scriptive Assembiv Drtwing, Model 715_

CLAMP RING HE AD CLOSURE

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flNSULATING '_INER I k2 I N. THK.(<.:N.)

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STEEL POP RIVETS (4) k eMOLDED RUBBE RIZEI H AI R FILLER

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x TOTAL WEl6HT WITH 616 - 105, INSUL ATING LINE;R DATA,:

WITH 6 44 - 102,

N S U L ATI ON WITH 5E5 -l05 HIG H T E M P.)O R M IL-1-2 819 M I L-l-27 61:

TECHNICA L OPERATIONS INC TYPE 8 SHIPPING CONTAINER

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MODEL 715 z_fs_72

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1.3.2 Description of Tech / Ops Model 533 and 713 Gamma Ray Projectors NOTE: The Model 713 gamma ray projector is a slightly modified Model 533 that is designed to operate using a Model A424-9 Iridiuw-192 source assembly. All other aspects of the Model 713 are identical to the Model 533.

The Tech / Ops Model 533 gamma ray projector is designed for use as l

a radiographic exposure device for radiographic sources in special form.

The Tech / Ops Model 533 Gamma Ray Projector measures 12.75 inches in r

length, 9.5 inches in height and 4.75 inches in width. The gross weight of the-container is 38 pounds. The projector contains 29 i

pounds of depleted uranium as shielding material.

192 The maximum capacity of the projector is 120 curies of Iridium as special form, Tech / Ops source assembly A424-1. This source assembly has previously been described to the Materials Branch, Division of Materials and Fuel Cycle Facility Licensing, U.S.

Nuclear Regulatory Commission, in conjunction with this gamma ray projector. In addition, the source assembly A424-1 utilizes a source capsule Model No. 60001 or 60004. These capsules have been

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described to the Transportation Branch, Division of Materials and Fuel Cycle Facility Licensing, U.S. Nuclear Regulatory Commission in conjunction with Tech / Ops Models 650 and 660 gamma ray projectors.

The radioactive source assembly is housed in a zircalloy "S" tube.

The "S" tube has an outside diameter of 0.467 inches and an inside of 0.385 inches.

The zircalloy tube is surrounded by depleted uranium used as shielding material. The uranium metal is cast around the zircalloy "S" tube. Reinforcement sleeves fabricated from zircalloy tubing, are installed over the "S" tube at the position where the "S" tube leaves the shield.

The depleted uranium shielu assembly is mounted on'an aluminum frame by means of two steel "U" bolts. The aluminum frame secures the shield in its proper position. The aluminum frame is mounted inside the shell of the gamma ray projector.

i Attached to the rear of the projector shell is the control cable connector and. lock assembly. The lock assembly is designed to prevent the source from being retracted through the assembly through an interference with the stop ball on the source assembly.

i Actuating the lock assembly creates an interference in front of 1-5 Revision 0 11 April 1980 i

0 the stop ball preventing the source assembly from moving in the forward direction. A key operated plunger style lock secures the control cable connector selector ring in the locked position.

As an additional security measure, a shipping plug is installed in the "S" tube from the opposite direction. The Teleflex wire is fabricated of such length as to provide a 1/8 inch preload when the shipping plug is fully threaded in its recepticle. The shipping plug and nut, are drilled for sealwire. They are seal-wired and provided with a tamper proof-seal during transport.

A radiation profile of a Model 533 Gamma Ray Projector Serial No.

348wasmadeusingaVic{ggeen592BSurveyMeter. The Model 533 contained 102 curies of Iridium. The measurements were as follows:

Surface

@ 1 Meter Top 20 1

Bottom 47 1

Front 26 1

Back 31 1

Left 82 1

Right 85 1

NOTE: All readings in units of Milliroentgens per hour Thus the radiation profile of the Model 715 shipping container containing a Model 533 gamma ray projector and 120 curies of Iridium-192 would be considerably lower and well within the regulatory limits.

The Model 533 gamma ray projector has been previously found acceptable for licensing by the Materials Branch, Division of Materials and Fuel Cycle Facility Licensing, USNRC. In addition the Model 533 has been authorized for use in the Model 715 shipping container by the Office of Hazardous Materials, United States Department of Transportation and issued IAEA CertificateofCompetentAuthorityNumberUSA/9039/B.lCopiesof these approval letters and certificate are included at the end of this application.

l 1.3.3 Description of Tech / Ops Model 616 Gamma Ray Projector Tech / Ops Model 616 gamma ray projector is designed for use as a radiographic exposure device for radiographic sources in special form. The Model 616 is transported inside Tech / Ops Model 715 shipping container.

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and 11.5 inches in length. The gross weight of the projector is 45 pounds. The projector contains 28 pounds of depleted uranium.

as shielding materfal.

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The maximum capacity of the projector is 200 curies of Iridium-192 as special form Tech / Ops source assembly 58101. This source assembly has been previously described to the Materials Branch, Directorate of Licensing, United States Atomic Energy Commission, in conjunction with this projector.

l The radioactive source assembly is housed in a CRES 304 tube which l

has an outside diameter of 0.312 inch and a wall thickness of 0.022 inch. This source tube is installed inside a depleted uranium shield.

The uranium shield. assembly is positioned between the shield nest and the shield housing cover. The shield nest and the shield hous-i ing cover are bolted together by means of tie rods which securely 1

position.both the uranium shield and the source tube.

The uranium shield is completely encased by a 1/8 inch thick mild steel housing assembly. This steel shield housing assembly centers the shield at the shield nest and is secured to the shield housing cover by means of six %-20 UNC hex head bolts. These bolts are lockwired in pairs to prevent inadvertent unthreading.

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Attached to the radioactive source is a source rod manufactured from tungsten. The source rod and coupler assembly provides shielding

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along the source tube and a means for connection to the source rod connector.

Attached to the shield housing cover is the lower cylinder housing.

This lower cylinder housing is attached to the shield housing cover by means of three %-20 UNC hex head bolts which are lockwired together.

I The lower cylinder housing houses the source rod connector which is used to move the source out of the storage position; it also houses the locking mechanism.

The lock mechanism consists of a standard Corbin key-operated plunger type lock (No. 02290) attached to a lock pin by means of a roll pin.

When in the locked position, the lock pin contacts the smaller diameter of the source rod connector. This produces an interference for the larger diameter of the source rod connector, and thus will not allow the source to relocate into the unshielded position. The l

lock mechanism is designed such that the lock cannot be engaged if the source is not in the shielded position.

A radiation profile of a.Hodel 616 gamma ray projector containing 200 curies of Iridium-192 was measured using a Victoreen 592 survey

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meter. The maasurements were as follows:

Location Contact At 1 Meter Top 168 5.0 Bottom 166 4.0 Front 160 4.0

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Back 120 5.0 Left Side 126 5.0 Right Side 168 5.0 NOTE: All readings in milliroentgens per hour Thus, the radiation profile of the Model 715 shipping container containing a Model 616 and 200 curies of Iridium-192 would be considerably lower and well within the regulatory limits.

l The Model 616 gamma ray projector has been previously found accept-able for licensing by the Materials Branch, Directorate of Licensing, United States Atomic Energy Commission. In addition, the Model 616 has been authorized for use in the Model 715 shipping container by the Office of Hazardous Materials, United States Department of Transportation, and issued IAEA Certificate of Competent Authority Number USA /9039/B. Copies of these approval letters and certificate are included at the end of this application.

1.3.4 Description of Tech / Ops Model 664 Gamma Ray Projector Tech / Ops Model 644 gamma ray projector is designed for use as a radiographic exposure device for radiographic sources in special form. The Model 644 is transported inside Tech / Ops Model 715 shipping container.

The Model 644 gamma ray projector measures 4.5 inches in diameter and 14.5 inches in length. The gross weight of the container is 49 pounds. The projector contains 33 pounds of depleted uranium as shielding material.

l The maximum capacity of the projector is 120 curies of Iridium-192 as special form Tech / Ops source assembly 58101. This source assembly has previously been described to the Materials Branch, Directorate of Licensing, U.S. Atomic Energy Commission, in conjunction with this projector.

The radioactive source assembly is housed in a CRES 304 source tube (pc. 10) which has an outside diameter of 0.312 inch and a wall thickness of 0.035 inch. This source tube is installed inside a depleted uranium shield.

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The depleted uranium shield is fabricated-in two parts from uranium metal. It is positioned by an aluminum back-up plate, a steel end cap and an aluminum shield spacer. The depleted uranium shield is encased in 1/8 inch thick cold drawn seamless steel tubing. The steel shield tube is attached to the end cap by means of six 10-32 UNC x 5/8" long stainless steel bolts which are sealwired i

together.

j The radioactive source assembly is attached to a tungsten source rod. This source rod provides shielding along the direction of the source tube and provides a means of moving the source from its l

stored position to its exposing position. The source rod is con-nected to the source coupler and this, in turn, is attached to i

the operating mechanism.

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In front of the source assembly along the source tube is a tungsten j

safety plug. This safety plug provides shielding along the forward direction of the-source tube and provides a means of securing the source in the storage position. The safety plug is held captive by the safety plug housing. This housing is fastened by means of l

jam nuts and lockwashers.

To ensure proper source position during transportation, the safety plug is secured against the radioactive source assembly. With the source assembly in the stored position, the tungsten safety plug is C_

inserted fully. A key-operated padlock is inserted through the

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safety plug housing to provide an interference with the safety plug tap, thus preventing the safety plug from being withdrawn. Thus, j

the source is prevented from moving in the forward direction.

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The source is prevented from moving in the rearward direction by the operating mechanism. The joint between the pinion arm and the connect-ing link contacts the tungsten source shield. This produces an inter-ference to source movement in the aft direction, and thus the source remains in its proper storage position during transport.

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A radiation profile of a Model 644 gamma ray projector, Serial Number 14, containing 108 curies of Iridium-192 was measured using a Victoreen t

592B survey meter. The measurements were as follows:

e Location Contact At 1 Meter i

l Top 78 1

Bottom 76 1

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Front 72 1

Back-60 2

i Left 74 1

Right 74 1

s NOTE: All readings in units of milliroentgens per hour l

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Thus the radiation profile of the Model 715 shipping container con-taining a Model 644 gamma ray projector and 120 curies of Iridium-192 l

would be considerably lower and well within the regulatory Ibnits.

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The Model 644 gamma ray projector has been previously found acceptable l

for licensing by the Materials Branch, Directorate of Licensing, United States Atomic Energy Commission. In addition, the Model 644 has been authorized for use in the Model 715 shipping container by the Office of Hazardous Materials, United States Department of Transportation and issued IAEA Certificate of Competent Authority Number USA /9039/B.

Copies of these approval letters and certificate are included at the i

end of this application.

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"M33 CERTIFICATE OF COMPLIANCE to CFr*71 For 8%adioic1ws Mastrials PgcLagos Cenif cate Number 1.(b) Revision No.

1.4 c) Package identification No.

1.id ) Pages No. 1.le) Total No. Pa; O

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0 0~30 "I

f f q A / QO10 /R ( )

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2. PRE AMBLE 2.lal This cenificate is issued to satisf y Sections 173.393a.173.394.173.395, and 173.396of the Department of Transportstion Hazard Materials Regulations (49 CFR 170-189 and 14 CFR 103) and Sections 146-19-10a and 146-19-100 of the Department of Transportation Dangerous Cargoes Regulations (46 CFR 146-149). as amended.

The packaging and contents described in item 5 below, meets the safety standards set forth in Subpart C of Title 10. Code of 2.fb)

Federal Regulations. Part 71. ** Packaging of Radioactive Materials for Transpon and Transportation of Radioactive Material Urder Certain Conditions."

This canificato does not relieve the consignor f-om compliance with any requirement of the regulations of the U.S. Decartment of 2.ic)

Transportesion or other agolicable reguistory agencies, incsuding the government of any country through or into whicri the packa9s will be transponed.

3. This certifscate is issued on the basis of a safety analysis repon of the package desegn or application-3.tal Prepared by (Name and address):

3.fb)

Title and ioentification of repon or application:

Technical Operations, Inc.

Technical Operations, Inc. application dated Northwest Industrial Park March 10,1975, as supplemented.

Burlington, Massachusetts 01803 3.(c)

Docnet No.

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CONDITIONS This cenificate is corditional upon the fulfilling of the roouirements of Subpan D of to cFR 71. as applicable, and the corditions spech 4

f in item 5 baiow.

5. Descriotion of Packaging arv1 Authorized Contents. Model humoer. Fiss.le Class. Other Condstions, ard Ref erencus:

(a) Packaging

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(1) Model No.: 715 (2)

Description A protective overpack for radiographic devices. The overpack consis'ts of an MS-27683-2,18-gage steel drum; 14-gage clamp closure ring fastened by a bolt; 1.5 inches of Mil-I-2781 or Mil-2819 high temperature insulation; and a molded rubberized hair filler material. Overall. dimensions of the overpack are approximately 15.5-inch diamet'er by 24-inch high.

Maximum weight including

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contents is 105 pounds.

(3)

Drawings The radiographic devices, as secondary packaging authorized for use in the overpack are constructed in accordance with the following Technical Operations, Inc. Drawings Nos.:

Model No.

Drawino Nos.

533 053301 616 061699 644 D64400 713 C71301 D53301

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l Page 2 - Certificate No. 9039 - Revision No. 3 - Docket No. 71-9039 0$

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(b) Contents (1) Type and form of material Irridium-192 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 (i) 120 curies contained in the Model No. 533, Model No. 644 or i

Model No. 713 radiographic device.

(ii) 240 curies contained in the Modal No. 616 radiographic device; 6.

Source assemblies for use in this packaging are limited to those assemblies as identified in Technical Operations, Inc. Drawing No. C42400, Rev. F, Sheet 2, and Sheet 3 of 3.

7.

Separate molded filters shall be used for each model type radiographic device to ensure a snug fit within the overpack.

I 8.

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

3 9.

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.

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10.

Expiration date: May 31,1980.

REFERENCES Technical Operations, Inc. application dated March 10, 1975.

Supplements dated:

April 11,1975 and November 16, 1977 l[

FOR THE U.S. NUCLEAR REGULATORY COMMISSION fA Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle ~and Material Safety DEC 1 UT7 Date:

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2.

Structural Evaluation 2.1 Structural Design

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2.1.1 Discussion Structurally the Model 715 consists of three components: a source capsule, gamma ray projector and outer packaging. The outer packag-ing consists of a molded rubberized hair filler and insulation liner contained in a steel drum. The source capsule is the primary con-tain= ant vessel. It satisfies the criteria for special form radio-active materic!. The gamma ray projector fulfills two functions.

It provides shielding for the radioactive material and with its lock assembly secures the source assembly in the proper shielded position.

The outer steel drum is fabricated from 18 gage (.048 inch thick) steel, MS27683-2, with inside dimensions of 15.38 inches diameter and 23.88 inches high. The steel drum is closed by means of a cover with gasket (MIL-5-6855) and secured by a clamp ring head closure.

The head closure is fastened by means of a bolt drilled for a seal wire to provide a tamperproof seal. The steel drum is lined with high temperature insulation, MIL-I-2781 or MIL-I-2819, on the sides and ends. The minimum thickness of insulation is 1% inches. Inside the insulation liner is a molded rubberized hair filler. This filler is molded to conform to the configuration of the gamma ray projector.

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to be transported (Models 533, 616, 644 or 713). A separate molded filler is employed for each model projector used.

The outer housing provides the structural strength of the package and also ensures that the gamma ray projector cannot be accidentally removed from the package and damaged. The inserts prevent against shifting of the contents during transport and also prevent damage to the contents. The gamma ray projector secures the source assembly ir. the shielded position and assures positive closure.

2.1.2 Design Criteria The Model 715 is designed to comply with.th'e requirements of 10CFR71 and IAEA Safety Series No. 6, 1973 Edition. The package is simple in design. There are no design criteria which cannot be evaluated by straight forward application of the appropriate section of 10CFR71 or IAEA Safety Series No. 6.

2.2 Weights and Centers of Gravity The Model 715 weighs 105 lbs.- (47.7kgs) with a Model 616 Gamma Ray Projector; 102 lbs. (46.3kgs) with a Model 644 Gamma Ray Projector; and 103 lbs. (46.8kgs) with a Model 533 or 713 Gamma Ray Projector.-

The center of gravity was determined empirically. It is located along the cylindrical axis at a distance of 12.0 inches (.61m) above the bottom surface nt the geometrical center of the package.

2-1 Revision 0 11 April 1980

P 2.3 Mechanical Properties of Materials The Model 715 housing is fabricated from cold rolled low-carbon sheet steel. This material has a yield strength of 65,000 pounds per square inch inch (448MN/m2).

(

Reference:

Machinery's Handbook, 21st Edition, P. 2118 Edgecom's Buyers Guide P. 264 Ryerson Data Book 1967, P. 17)

Drawings of the source capsules shipped in the Model 715 package are enclosed in Section 2.10.

For descriptions of the gamma ray projectors see Section 1.3.

The source assemblies all consist of a source capsule fabricated from Type 304 or Type 304L stainless steel with a yield strength of 35,000 pounds per square inch (241NN/m2). The source capsule is swaged to a "Teleflex" steel cable. The capsules are sealed by tungsten-inert gas welding. The swaged coupling is tensile tested on a production basis to 75 pounds (334 newtons).

(See Section 7.4).

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

The materials used in the construction of the Model 715 are high temperature insulation (NIL-I-2819 or MIL-12781) molded rubberized hair as filler and low carbon steel for the outer housing. There will be no significant chemical or galvanic action between any of these components.

2.4.2 Positive Closure The source assemblies of the gamma ray projectors in the Model 715 overpack cannot be exposed without opening a key operated lock on each type of projector. Access to the lock on the projector requires removal of the Model 715 cover. The cover is sealwired which provides a tamperproof seal.

2.4.3' Lifting Devices The Model 715 is designed without any lifting devices. The entire shipping container must be lifted from either end during transport.

2.4.4 Tiedown Devices The Model 715 has no tiedown devices. To secure container during transport requires the use of restraining devices that wrap around l

container.

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?.5 Standards for Type B and Large Quantity Packages 2.5.1 Load Resistance Considering the package as a simple beam supported on both ends with a uniform load of five times the package weight evenly dis-tributed along its length, the maximum stress can be computed from:

F1 s =

8Z where s: Maximum Stress F: Total Load (525 lbs. 2.32kN) 1: Length of Beam (25.24 in.; 610mm)

Z: Sectinn Modulus (8.55 in3 ; 140mm3)

(

Reference:

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

The load is assumed to be 525 pounds (2.32kN). The container is assumed to be a hollow cylinder with an outside diameter of 15.13 inch (384mm), a wall thickness of 0.048 inch (1.2mm) and a length of 25.24 inches (641mm). consequently the section modulus of the beam is.8.55 in3 (140mm3).

Therefore the maximum stress generated in the beam is 194 pounds per square inch (1.33MN/m2) which is far below the yield strength of the material at 65,000 pounds per square inch (448MN/m2).

~

2.5.2 External Pressure The Model 715 overpack and the Model 533, 616, 644 and 713 Gamma Ray Projectors are open to the atmosphere. Therefore, there will be no differential pressure acting on them. The collapsing pressure of the source capsules is calculated assuming that the capsules are thin wall tubing with a wall thickness equal to the minimum depth of weld penetration (.020 inch; 0.5mm). The collapsing pressure is calculated from:

p = 86,670 t:,

1386 d

where p: Collapsing pressure in pounds per square inch t: Wall thickness (0.020 inch) d: Outside diameter (0.25 inch) i l

(

Reference:

Machinery's Handbook, 21st Edition., p. 440)

The collapsing pressure of the source capsules is calculated to be 5547 pounds per square inch (38MN/m2). Therefore, the source capsules can withstand an external pressure of 25 pounds per square inch gauge.

.L 2-3 Revision 0 11 April 1980 i

t l

t 2.6 Normal Conditions of Transport 2.6.1 Heat I

The thermal evaluation of the Model 715 is performed in Chapter 3.

From this evaluation, it can be concluded that the Model 715 can with-l stand the normal heat transport condition.

2.6.2 Cold

{

The metal used in the manufacture of the Model 715 can withstand a temperature of -40 F (-40 C).

i Thehightemperatureinsulationandmoldedrubberizedhafrfiller inserts can also withstand temperatures of less than -40 F (-40 C).

Therefore, it is concluded that the Model 715 shipping container l

will withstand the normal transport cold. conditions.

l i

2.6.3 Pressure The Model 715 containing the Model 533, 616, 644 or 713 Gamma Ray Projector is open to the atmosphere; thus, there will be no differen-tial pressure acting on the package. In Section 3.5.4, it is demonstrated that the source capsules are able to withstand an external pressure reduction of 0.5 atmospheres (50.7kN/m2).

2.6.4 Vibration l

The Model-715 (Certificate of Compliance USA /9039/B) has been in use for five years. During that time, there have been no vibrational

+

failures reported.

On that basis, we contend that the Model 715 will not undergo a

[

vibrational failure during transport.

2.6.5 Water Spray Test The water spray test was not actually performed on the Model 715.

We contend 'that the materials used in construction of the Model 715 are all highly water resistant and that exposure to water will not l

reduce the shielding'or affect the structural integrity of the package.

During the five year period the Model 715 has been in use, no failures due to exposure to water have been reported.

2.6.6 Free Drop The drop analysis performed in Section 2.7.1 is sufficient to satisfy i

the requirements of the normal transport free drop condition. On this i

2-4 Revision 0 11 April 1980

l basis, we conclude that the Model 715 will withstand the free drop without loss of shielding effectiveness or loss of package integrity.

2.6.7 Corner Drop l

Not Applicable l

2.6.8 Penetration A penetration test of the Model 715 was not actually performed. We contend that the materials used in the construction of the Model 715 l

are highly resistant to penetration. Furthermore, the nature of the shipping package is such that the. source assembly is secured inside the gamma ray projector which is centered inside the container surrounded by 2% inches of insulation and rubberized hair filler.

{

It is impossible to penetrate the shipping container and affect the integrity of the source assembly inside the gamma ray projector.

]

2.6.9 Compression The gross weight of the Model 715 and the Model 616 Gamma Ray Projector is 105 pounds (48kg). The maximum horizontal cross sectional area is 180 in2 (.12m2). Thus five times the weight of the package (525 lbs; r

2339 newtons) is greater than 2 pounds per square inch times the maximum i

I l

horizontal cross section area (360 pounds; 1604 newtons)..

f The maximum stress generated on a cylinder of equal cross sections j

and a uniformly distributed load over the end surfaces can be computed from:

c = 0.24F l

t where c : maximum stress generated in the cylinder F: load applied to the cylinder (525 pounds; 2339 newtons) t : thickness of plate (.048 inch; 1.2mm)

(

Reference:

Machinery's Handbook, 21st-Edition, P.,436)

From this relationship, the maximum stress generated in the cylinder 2

is found to be 54688 pounds per square inch (377MN/m ) whicg is less than the yield strength of the material (65,000 psi; 448MN/m ).

There-fore, it can be concluded that the compression condition will not affect the package.

i i

4 2-5 Revision 0 11 April 1980 i

i

2.7 Hypothetical Accident Conditions 2.7.1 Free Drop r

Prior to the first submittal of the Model 715 shipping container to the Office of Hazardous Materials, U.S.D.O.T. in February, 1972, the Model 715 was subjected to a drop test through'a distance of 30 feet onto a steel plate. The Model 715 Shipping Container contained a Model 616 Gamma Ray Projector during the test. Damage was limited to minor deformation and some crushing of the insulating liner.

There was no increase in radiation intensity nor loss of radioactive material.

I 2.7.2 Puncture A puncture test was not actually performed on the Model 715. It is concluded that a drop from a height of.one. meter onto a six inch diameter steel billet would not produce any greater damage than the 30 foot Free Drop Test. (See Section 2.6.8).

2.7.3 Thermal The thermal analysis is presented in Section 3.5.

It is shown that the melting temperatures of the materials used in the construction

( -

of the Model 715, except the molded rubberized hair filler, are all in excess of 1475 F (800 C).

To demonstrate that the radicactiva source assemblies will remain shielded following the hypotletical thermal accident, the following analysis is presented. At t.;e conclusion of the thermal test, it was shown that the rubberized hair filler partially melts. The high thermal insulation remained intact. The Model 616 Gamma Ray l

Projector was charred on the exterior surfece and remained functional.

The locking. assembly kept.the source assembly secured in the shielded r

position.

Thus, it is concluded that the Model 715 satisfactorily 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 tests designed to induce mechanical stress (e.g. free drop test) caused minor deformation, but no reduction in the safety features of this package. The thermal condition will result in no reduction of the safety of the package.

2-6 Revision 0 11 April 1980

a It can be concluded that the hypothetical accident conditions have no adverse effect on the shielding effectiveness or. structural integrity of the package.

2.8 Special Form The Model 715 is designed for use with the Model 533, 616, 644 or 713 Gamma Ray Projectors containing source assemblies Model A424-1, 58101, or A424-9. These source assemblies have all been certified as Special Form Radioactive Material under IAEA Certificate of Competent Authority No. USA /0154/S. A copy of this certificate is included in Section 2.10.

2.9 Fuel Rods i

Not Applicable i

I i

I t

.2 - 7 Revision 0

(-

11 April 1980 l

t

2.10 Appendix Descriptive Assembly Drawings of Sources USNRC Safety Evaluation Report IAEA Certificate of Competent Authority USA /0154/S i

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J 2 - 11 Revision 0 11 April 1980

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.(CURIES)

STYLE A424.-l.

.120.E _~ j g _OR. g,373.

7g A424-9.

... J 20 B60001_ OR 860004 ~~

1225._ -7k..

A81401.

I20

.l.875 7T6'-

NOT~ APPLICABLE;MTA1DED A68509

. 120 C685lO ME DRIVE CABLE

~ B6970)~

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RADIATION PRODUCTS DIVISION sf BURLINGTON MA 01803 FINISH DWG TITLE oa^*" "'

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MATERIALS TECHNICAL OPER ATIONS INC.

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RADIATION PRODUCTS DIVISION

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BURLINGTON. MA 01803 FIN!SH N

DWG TITLE N

192 ggy

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IRIDIUM SOURCE REFERENCE

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U.S. NUCLEAR REGULATORY C0tNISS10N SAFETY EVALUATION REPORT Transportatior. Branch Office of Nuclear Material Safety and Safeguards l

Technical Operations, Inc.

Model 715 USA /9039/B Enclosure to ltr dtd MAY 2 6 1975 Summary

.By application dated March 10, 1975, Technical Operations, Inc.,

Burlington, Massachusetts, requested authorization to deliver Special Form Iridium-192 sources to a carrier for transport. The shipping packaging consists of a Model 715 overpack for Tech / Ops Models Nos.

533, 616, and 644 radiographic devices.

Based on the statements and q'

representations contained in the application, we have concluded that the Model 715 overpack meets the Type B packaging requirementslif 10 CFR Part 71, subject to the conditions contained herein.

fg Submiitals Technical Operations, Inc. application dated March 10, 1975.

Supplement dated April 11, 1975.

Drawing List The radiographic devices, as secondary packaging, authorized for use in the overpack are constructed in accordance with the following e

j,!

Technical Operations, Inc. drawings:

i Model Drawing No.

.g I

533 D53301 1

616 D61699 644 D64400 i

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Description The Model 715 overpack provides thermal and impact protection for Tech / Ops Models Nos. 533, 616, and 644 radiographic devices. Main components of the overpack consist of an MS-27683-2,18-gage, steel drum; 14-gage clamp ring closure fastened by a bolt drilled for seal 9

wire to provide a tamper proof scal; 1.5 inches of Mil-I-2781 or i

Mil-2819 high temperature insulation; and a separate molded, rubberized hair filler material for each radiographic device. Overall 3

dimensions of the overpack are approximately 15.5 inches in diameter

. ;4'j by 21 inches high. The maximum weight, including contents, is approxi-

{,,

mately 105 pounds, tt Package Contents Contents consist 'of Iridium-192 sources in special form housed within radiographic devices that serve as secondary packagings. Maximum e

contents for the package containing Models Nos. 533 ara 644 radiographic devices is 120 curies. Maximum contents for the paGage containing Model.No. 616 radiographic device is 240 curies.

Structural The applicant 's evaluation of the impact protection provided to the radiographic devices by the overpack is based on actual test. The overpack containing a Model 616 radiographic device was dropped 30 feet onto a steel nlate.

Damage reported was limited to minor deformation and some crut..ng of the insulation liner.

No increase in radiation

, [,

intensity nor loss of radioactive material was experienced.

Review of

.the design features of the radiographic devices has substantiated that positive design mechanisms are included to prevent repositioning of the source assemblics once the sources are locked into position.

J' Thermal

~i For the normal conditions of transport 'there will be no adverse thermal-effect on the package.

's :.

The fire test at 1475*F for one-half hour was performed on the overpack

-i.

containing a Model 616 radiographic device.

Internal temperature was monitored using two arrays of "Tempil" pellets.

One array placed on the radiographic device indicated temperatures less than 350*F.

The other array of pellets placed between the rubberi:cd hair and the insulation liner indicated temperatures less than 700*F.

The radio-graphic device was unaffected by the heat and no release of radioactive material nor increase in radiation intensity was observed by the applicant.

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Shielding The applicant performed radiation surveys on all three radiographic devices without the overpack.

Reported test results ware within the maximums as prescribed in 10 CFR Part 71.

Placement of the radio-graphic devices within the overpack will result in further reduction of the radiation levels.

Conditions Based on the above tests and presentations, we agree that the Model 715

, il overpack for the Models Nos. 533, 616, and 644 radiographic devices meet the Type B package requirements of 10 CFR Part 71, subject to j

the following conditions:

h 1.

The package contents are limited to the source assemblics as described on Technical Operations, Inc. Drawing No. C42400, Rev. F, Sheet 2 and Sheet 3 of 3 sheets.

.I d

2.

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

p 3.

Separate molded fillers shall be used for each model type radiographic device.

J

. =,

IA [M Charles E. MacDonald, Chief if Transportation Branch Division of Materials and e '.

Fuel Cycle Facility 1.icensing 8!

9 yg 2 8 1975 Date

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DEPARTMENT OF TRANSPORTATION

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RCSEARCH AND SPECI AL PROCiR AMS ADMINISTR/. TION r

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g' WASHINGTON.

D.C.

2o500 i' U

'...',,.'/

IAEA CERTIFICATE OF COMPETENT AUTHORITY 4

I Special Forn Radioactive Material Encapsulation

,,y n yo, Certificate Number USA /0154/S This certifies that the encapsulated sources, as described, when loaded with the authorized radioactive contents, have been demon-strated to meet theregulatoryrequirementyforspegialforn radioactive material as prescribed in IAEA and USA regulations for the transport of radioactive materials.

1.

Source Description - The sources described by this certificate are identified as the Technical Operations, Inc., Models which are described and constructed as follows:

Model No.

Capsale Style Approximate Size (in inches, diameter x lengt1 A424-1 B60001 or B60004

.25 x.97 A424-6 B60001 or B60004

.25 x.97 A424-9 B60001 or B60004

.25 x.97 A424-20 B60001 or B60004

.25 x.97 A38101 B60006 Pellet, Wafer or Large Wafer

.25 x.90 A68309 C68310 Pellet or Wafer

.25 x.78 A81401 B60001 or B60004

.25 x.97 B69701 B60001 or B60004

.25 x.97 i

All capsules are constructed of either 304 or 304L stainless steel and conform with the following design drawings:

Capsule Style Drawing Number i

B60001 B60001 - 1 Rev. H and - 2 Rev. T B60004 B60001 - 1 Rev. H and B60004 - 1 Rev. D B60006 Pellet B60006 - 1 Rev. H and B60001 - 2 Rev. F B60006 Wafer B60006 - 1 Rev. H and B60004 - 1 Rev. D B60006 Large Wafer B60006 - 2 and B60001 - 2 Rev. F C68310 Pellet C68310 Rev. B and B68310-3 C68310 Wafer C68310 Rev. B j

II.

Radioactive Contents - The authorized radioactive contents of these sources consist of not more than the following amounts of Iridium-192 as solid metal:

I e

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., _'.j Cartificate Numbar USA /0154/S

... 4 Pega 2 I

'Model No.

Contents (Curies)

[()

A424-1 120 A424-6 120 A424-9 120 A424-20 240 A58101 240 A68309 120 I

A81401 120 B69701 120 s

III. This certificate, unless renewed, expires December 31, 1981.

This certificate is issued in accordance with paragraph 803 of the l

IAEA Regulations, and in response to the November 3, 1978, petition by Technical Operations, Inc., Burlington, Massachusetts, and in consideration of the associated information therein.

Certified by:

r

-.I

/

l R. R. Rawl, Health Thysicist (Date)

U. S. Department of Transportation

(

Office of Hazardous Materials Regulation Washington, D. C.

20590.

i l

I

?

I" Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition", published by the l

International Atomic Energy Agency (IAEA), Vienna, Austria.

I 2

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

I i

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3.

Thermal Evaluation 3.1 Discussion The Model 715 is a completely passive thermal device and has no mechanical cooling system nor relief valves. All cooling of the package is through free convection and radiation. The heat source is 240 curies of iridium-192. The corresponding decay c is 2.06 watts.

3.2 Summary of Thermal Properties of Materials The melting points of the metals used in the construction of the Model 715 are:

Zircalloy 3350 F (1845 C)

Steel 2453 F (1345 C)

Uranium 2070 F (1133 C)

Copper 1940 F (1060 C)

Bronze 1840,F (2005,C)

Aluminum 1220 F

( 660 C)

Beryllium Copper 1600 F

( 870 C) 3.3 Technical Specifications of Components Not Applicable i

3.4 Normal Conditions of Transport 3.4.1 Thermal Model 3.4.1 Thermal Model i

The heat source in the Model 715 is a maximum of 240 curies of iridium-192. Iridium-192 decays with a total energy liberation of 1.45 MeV per disintergration of 8.58 milliwatts per curie.

Assuming that all of the decay energy is transformed into heat, the heat generation rate for the 240 curies of iridium-192 would be 2.06 watts.

To demonstrate compliance with the requirements of paragraphs 231 and 232 of IAEA Safety Series No. 6,1973 for Type B(U) packaging, an analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

To demonstrate compliance with the requirements of paragraph 240 of IAEA Safety Series No. 6,1973 for Type B(U) packaging, a separt,te analysis is presented in Section 3.6.

The thermal model employed is described in that analysis.

k 3-1 Revision 0 11 April 1980

O I

3.4.2 Maximum Temperatures The ma ximum temperatures encountered under normal conditions of transport will have no adverse effect on structural integrity or shielding. As shown in Section 3.6, the maximum temperature in the shade would be less than 41 C and the maximum temperature when insolated would be less than 74 C.

3.4.3 Minimum Temperatures The,minimug normal operating temperature of the Model 715 is

-40 F (-40 C). This temperature will have no adverse affect on the package.

3.4.4 Maximum Internal Pressures Normal operating conditions generate negligible internal pressures.

Any pressure generated is significantly below that of the hypo-thetical accident pressure, which is shown to result in no loss of shielding or containment.

3.4.5 Maximum Thermal Stresses The maximu m temperatures that occur during normal transport are low enough to insure that thermal gradients will cause no significant thermal stresses.

3.4.6 Evaluation of Package Performance for Normal Conditions of Transport i

The thermal conditions of normal transport are insignificant from a fu ational viewpoint for the Model 715. The applicable conditions of IAEA Safety Series No. 6, 1973 for Type B(U) packtges have been l

shown to be satisfied by the Model 715.

3.5 Hypothetical Accident Thermal Evaluation l

3.5.1 Thermal Model A Model 715 package containing a Model 61g gamma ray projector was subjected to a temperature of 800.C (1475 F) for a period of thirty minutes.

3.5.2

. Package Conditions and Environment The Model 715 underwent no significant damage during the free drop and puncture tests. The package used in this test was considered undamaged.

3-2 Revision 0 11 April 1980 I

0 3.5.3 Package Temperatures As indicated in Section 3.5.1, the entire Model 715 package con-taining a Model 616 projector was subjected to a thermal test of 800 C (1475 F) for a period of 30 minutes by Whittaker Corporation, Nuclear Metals Division, Concord, MA.

The internal temperature was monitored using two arrays of "Tempil" pellets. One array, plaged on the Model 616, indicated that a temperature in excess of 149 C (300 F) but less than 177 C (350 F) had been reached. The other array, placed between the rubberized hair filler and the insulation lineringicatedatemperatureinexcessof343C(650F)butless than 371 C (700 F) had been reached.

3.5.4 Maximum Internal Pressures The Model 715 packaging is open to the atmosphere. Therefore, there will be no pressure buildup within the package. In Section 3.6, an analysis of the source capsules under the thermal test condition demonstrateg that the maximum internal gas pressure at 800 C is 55 psi (380kN/m ).

The critical location for An internal pressureof55 psi (380kN/m{ailureistheweld.

2

) will generate a gaximum stress of. 291pai (2.0MN/m ).

At a temperature of 870 C (1600 F),

theyie}dstrengthofType304stainlesssteelis10,000 psi (69MN/m ).

Thus, at 800 C, the maximum stress in the source capsule would be only 3% of the yield strength of the material.

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 715 underwent no loss of structural integrity nor loss of shielding during the hypothetical thermal accident test. There was no release of radioactive materialnor increase in radiation intensity.

As the temperature inside the insulation remained below 371 C (i.e. below the melting temperature of aluminum), it is concluded that the Model 715 would withstand the thermal accident condition when containing a Model 533, Model 644 or Model 713 projector.

3-3 Revision 0 11 April 1980

3.6 APPENDIX 3.6.1 Model 715 Type B(U) Thermal Analysis: Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1971 3.6.2 Model 715 Type B(U) Thermal Analysis: Paragraph 240 of IAEA Safety Series No. 6, 1973 3.6.3 Iridium Source Capsules Thermal Analysis 3.6.4 Test Report: Model 715 Thermal Test 3-4 Revision 0 11 April 1980

+

4 3.6.1 Model 715 Type B(U) Thermal Analysis Paragraphs 231 and 232 of IAEA Safety Series No. 6, 1973 i

This analysis demonstrates that the maximum surface temperature of the Model 715 will not exceed 50 C with the package in the shade and an ambient temperature of 38 C.

To assure conservatism, the following are used:

1) The entire decay heat (2.06 watts) is deposited in the exterior faces of the Model 715.

2) The interior of the Model 715 is perfectly insulated and heat transfer occurs only from the exterior wall to the atmosphere.

3) Because each face of the package eclipses a different solid angle, it is assumed that twenty five percent of the total heat is deposited in the smallest face (top).

4) 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 (0.515 watts) h:

Free convectiy*e hegt tS*")8f'r * 'ffici'"t f r air (1.67(6T) w/m C

A$: Area of the face of interest (0.12m )'

T,: Maximum temperature of the wall of the package T,: Ambient temperature (38 C) 1 From this relationship, the maximum temperature of the wall is 40.2 C.

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

3-5 Revision 0 11 April 1980 n;=: w u.

. w pe-.' m w,

m 4

t 3.6.2 Model 715 Type B(U) Thermal Analysis Paragraph 240 of IAEA Safety Series No. 6, 1973 I

This analysis demonstrates that the maximum surface temperatures of thehodel715wilgnotexceed82Cwhenthepackageisinanambient temperature of 38 C and insolated in accordance with paragraph 240 of IAEA Safety Series No. 6, 1973.

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

2 i

1) Thepackageisinsolatedagtherateof775w/m2 (800 cal /cm -12h) 2 on the top surface, 388w/m (400 cal /cm - 12h) on the sides, and no insolation on the bottom.

2) The decay heat load is considered negligible.

i

3) The package has a painted steel surface.

The solar absorptivity is assumed to be 0.9.

l The solar emissivity is assumed to be 0.8.

l

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 e

(

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 right circular cylinder resting on an gnd. Thesurfaceareasofthetopandbogtom are each 0.12m. The surface area of the side is 0.74m.

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

q in q out

=

9 +9 c r where q: Convective Heat Transfer c

q,: Radiative Heat Transfer The heat load applied.to the package is q in.= = q,.

where

=: absorptivity (0.9) q,:

Solar heat lead (380 watts)-

x 3-6 Revision 0 11 April 1980

The convective heat transfer is:

(

} top

• sides (T - T,)

S c

where h: Convective heat transfer coefficient A: Area of Surface of interest T: Temperature of wall y

T,: Ambient Temperature The heat transfer due to radiation is:

4 4) q = cc A(T

-T r

w w

where a: Stefan Boltzmann Constant (5.669 x 10 w/m2 O ')

-O k

c: Emissivity (0.8)

Iteration of thi6' relationship demonstrates that the wall temperature of the Model 715 is 73.22 C which satisfies.the requirement of paragraph 240 of IAEA Safety Series No. 6, 1973.

3-7 Revision 0 11 April 1980 m,m

.M ' ~4Qk ce 2 -u D.

'^ &

,5h t

l The hoop itress can be found by:

I 2c: hoop stress h

1

length of the cylinder i

t

thickness of cylinder From thig(relationship, the hoop stress is calculated to be i

1.96MN/m 284 psi).

At a temperature of 1600 F (870 C), the yield strength of type i

304 stainless steel is 10,000 psi (69MN/m'). Thus, under the conditions of paragraph 238 of IAEA Safety Series No. 6, 1973, the stress generated is less than 3% of the yield strength of the material.

i i

j i

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i 3-9 Revision 0 11 April 1980

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JR tvucLcan raCI ALS thVISIOiJ WhCT CCNr pac taxc;acsu; git: oi/ut TE L E P H O N t skit 4 3b9 5410 T m ei.,34/iosh 23 February 1972 c.m, o

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Technical Operations, Inc.

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Radiation Products Division South Avenue Burling ton,14 ass achuset ts Attention:

J. L iina

Subject:

Siniulated Fire Test of T/0 Shipping Container Gentleinen:

1 This '.etter is to confin'n IlllMD's confonnance to the scope of work q

described'in T/0 P.O. RPD 9620.

s DESCRIPTIO!!:

1.) The 7/0 supplied shipping coritainer was hand loaded into a l

preheated, 36 cubic foot resis tance heated furnace, at 1475*f.

i-2.)

/

The unit was held at teroperature for 30 ininutes af ter an initial 10 ininute recovery period.

3.) Tine container was ren.oved from the furnace. hot, and allowed i

to cool in air to room teinperature.

Very truly yours.

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(..b h U, fcc..'.-u

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yJohnG. Powers Project Engineer

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Hodel 715 Thermal Test a.

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(With Model 616 Gamma Ray Projector) l ;. * * '* 'c.-

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4.

Containment N

4.1 Containment Boundary 4.1.1 Containment Vessel The containment system for the Model 715 is the radioactive source assembly as listed in Section 1.2.3. of this application. The actual containment for the radioactive material is the welded source capsule as shown in Section 2.10.

These source assemblies are certified as special form radioactive materials (IAEA Certificate of Competent Authority No. USA /0154/S).

The capsules are constructed of either Type 304 or Type 304L stainless steel. The capsules are rounded cylinders with a diameter of 0.25 inch (6.35mm) and lengths of either 0.90 inch (22.9mm) or 0.97 inch (24.6mm).

4.1.2 Containment Penetrations There are no penetrations of the containment.

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4.1.3 Seals and Welds The containment is seal welded by a tungsten inert gas welding process which is described in Tech / Ops Standard Source Encapsulation Procedure (Section 7.4).

The minimum weld penetration is 0.020 inches (0.51mm).

4.1.4 Closure Not applicable 4.2 Requirements for Normal Conditions of Transport 4.2.1 Release of Radioactive Material The source assemblies have satisfied the requirements for special l

form radioactive material as delineated in IAEA Safety Series No. 6, j

1973 edition and 10CFR71. Therefore, there will be no release of l

radioactive material under the normal conditions of transport.

4.2.2 Pressurization of the Containment Vessel Pressurization of the source capsules under the conditions of the hypothetical thermal accident was demonstrated to generate stresses well below the structural limits of the capsule (See Section 3.5).

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

-4.2.3 Coolant Contamination Not Applicable s

4-1 Revision 0 11 April 1980 33 33.;

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i 4.2.4 Coolant Loss b

Not Applicable

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4.3 Containment Requirements for the Hypothetical Accident Conditions 4.3.1 Fission Gas Products Not Applicable i

4.3.2 Releases of Contents

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The hypothetical accident conditions of 10CFR71, Appe2 dix B will result in no loss of package containment an shown in Sections 2.7.1, i

2.7.2 and.3.5.

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Shielding Evaluation 5.1 Discussion and Results The Model 715 is designed for use as a Type B shipping container for the transport of Tech / Ops Models 533, 616, 644 and 713 gamma ray projectors containing Iridium-192 as special form sealed radioactive sources. The radioactive source assembly is contained inside the gamma ray projector. The gamma ray projector provides shielding for the radioactive source and also provides a means of locking the radioactive source in its proper storage position.

Descriptions of the Models 533, 616, 644 and 713 gamma ray projectors are provided in Section 1.3.

A radiation profile of Model 715 Serial No. 245 containing 208 curies of Iridium-192 in a Model 616 gamma ray projector was done. The re-sults of this survey are presented in Section 5.5.1.. Extrapol.etion to the maximum capacity of 240 curies for the Model 616 gamma ray projector is presented in Table 5.1.

The results demonstrate that the radiation levels from the Model 715 package with 240 curies of Iridium-192 in the Model 616 gamma ray projector are well below the regulatory limits for a shipping container.

As the Model 715 has no neutron source, the gamma dose rates are the total dose rates which are presented.

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

At Surface At One Meter Side Top Bottom Side Top Bottom 26 9

9 0.8 1.0 0.6 5.2 Source Specification 5.2.1 Gamma Source The gamma source is Iridium-192 in a sealed capsule as special form in quantities up to 240 curies.

5.2.2 Neutron Source Not Applicable l

5.3 Model Specification

's Not Applicable 5-1 Revision 0 11 April 1980

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5.4

. Shielding Evaluation The Model 715 shielding evaluation was performed on Model 715 Serial No. 245 -containing 208 curies of Iridium-192 in a Model 616 gamma ray projector.

The results of this survey (Section 5.5.1) demonstrate that the dose rates surrounding this package are within the regulatory requirements.

Prior to the first submittal of the Model 715 shipping container to the Of fice ' of Hazardous Materials, U.S.D.O.T.,

in February 1972, a radiation profile was made on this package after being subjected to hypothetical accident conditions. The Model 715 was subjected to a free drop of 30 feet onto a stee; plate. The Model 715 shipping container contained a Model 616 gamme ray projector during the test.

Damage was limited to minor deformation and some crushing of the insulating liner. There was no increase in radiation intensity and no loss of radioactive. mat.erial.

(Section 2.10).

5-2 Revision 0 11 April 1980 i

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. 5.5 Appendix 5.5.1 Radiation Profile - Model 715 Serial Number 245 1

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e 5.5.1 RADIATION PROFILE HODEL 715:

SERIAL NO. 245 Top t

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Sides Sides e

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Bottom Containing Model 616 Gama Ray Projector Serial No. 315 Source Model 58101 Serial No. S-2727 Activity:

208 Curies on 13 Mar 1980 Maximum Dose Rates (mR/hr)

O Surface

@ One Meter Top 8

Top 0.9 Sides 23 Sides 0.7 Bottom 8

Bottom 0.5 Measurements were made with an AN/PDR-27(J) Survey Instrument.

5-4 Revision 0 11 April 1980 s..

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Criticality Evaluation Not Applicable l

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~E3 7.

Operating Procedures 4

7.1 Procedures for Loading the Package The procedure for fabricating the special form source capsule is presented in Section 7.4.

The procedure used in preparing the Model 715 shipping container.for transport is presented in Sec-tion 7.4.

7. 2.... Procedures for Unioading the Package The procedures for unloading the Model 715 shipping container is presented in Section 7.4.

7.3 Preparation of an Empty Package for Transport Not Applicable 7-1 Revision 0 11 April 1980 l L l'*

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.a 7.4 Appendix Procedure for Encapsulation of Sealed Sources Model 715 Operating Instructions t

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RADIATION SAFETY MANUAL Part II In Plant Operations Section 2 ENCAPSULATION OF. SEALED SOURCES A.

Personnel Requirements Only an individual qualified as a Senior Radiological Technician shall perform the operations associated with the encapsulation of 192 Iridium. There must be a second qualified Radiological Technician available in the building when these operations are being performed.

B.

General Reauirements The 192 Iridium loading een shall be used for the encapsulation of solid metanic 192 Iridium and the packaging of sealed sources such as 170 Thulium, 137 esium and 169Ytterbiu=. Solid metallic Cobalt 60 C

not exceeding one curie may be handled in this cell also.

The maximum amount of 192 Iridium to be handled in this cell at an,y one time shall not exceed 1000 curies. The maximum amount of 13'Cs

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to be handled in this cell at any one time shall not exceed 100 curies.

This cell is designed to be operat,ed at 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 transfer containers and encapsulated sources transferred to approverl source containers.

When any of the "through-the-vall" tools such as the velding fixture or transfer pigs 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.

C.

Preparatory Procedure 1.

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

2.

If the veldin6 fixture or the electrodes have been changed, perform the encapsulation procedure omitting the insertion of any activity. Examine this du==y capsule by sectionin6 thru k-veld.' Weld penetration must be not less than 0.020 inch.

7

.3 Revision 0 11 April 1980

l If veld is sound and penetration is at 1 east 0.020 inch, the preparation of active capsules may proceed.

If not, the condition responsible for an unacceptable veld must be corrected and the preparatory procedure repeated.

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

Thisisabout}inchofwaterforanewfilter. When this pressure differential rises to about 2 inches of water, the filter must be changed.

D.

Encapsulation procedure 1.

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

2.

Degrease capsule components in the Ultrasonic Bath, using 4 sopropyl alcohol as degreasing agent, for a period of 10 0

minutes.

Dry the capsule components at 100 C for a minimu=

of twenty minutes.

3 Insert capsule cceponents.into hot cell with the posting bar.

4.

Place capsule in veld positioning device.

5 Hove drawer of source transfer container into hot cell.

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6.

Place proper amount of activity in capsule.

Disposable funnel must be used with pellets and a brass rivet with vafers to prevent contamination of veld zone.

7 Remove unused radioactive material from the hot cell by with-drawing the drawer of the source transfer container from the cell.

8.

Remove f m el or rivet.

9 Assemble capsule components.

10. Weld adhering to the following conditions:

a.

Electrode spacing.021" to.024" centered on joint 1002"; use jig for this purpose.

b.

Preflow argon, flush 10 seconds.

c.

Start 15 amps.

d.

Weld 15 amps.

e.

Slope 15 amps.

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post flow 15 seconds 7-4 Revision 0 11 April 1980 -

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11. Vicunny inspect tha v21d. An cec 2pt2blo veld must be continuous vithout crat2 ring, cracks or evidInca of blev out. If th6 veld 2

is defective, the capsule must be cleaned and revelded to V

neceptable conditions or disposed of as radioactive vaste.

12.

Check the capsule in hei6ht gauge to be sure that the veld is at the center of the capsule.

I 13 Wipe exterior of capcule with flannel patch vetted with EurA solution or equivalent.

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14. Count the patch with the scaler counting system. Patch must show no more than.005p Ci of contamination. If the patch shows more than.005 Ci the capsule must be cleaned and reviped.

4 If the revipe pateb stin shows core than 0.005 pCi of contamina-tion, steps 8 through 11 must be repeated.

15 Vacuum bubble test the capsule. Place t he velded capsule in e

a glass vial containing isopropyl alcohol. Apply a vacuum of 15 in Hg(Gauge). Any visual detection of bubbles vill indicate a leaking source. If the source is determined to be leaking, f

place the source in a dry vacuum vial and boil off the residual, alcohol. Reveld the capsule.

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16. Transfer the capsule to the svaging fixture. Insert the vire 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. Bctension under

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the load shall not exceed 0.1 inch.

If the extension exceeds O.1 inch, the source must be disposed of as radioactive. vaste.

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 maximum response. Record the meter reading. Ccepute the activity in curies and fin out a temporary source tag.

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19 Using remote control, eject the source from cell into source

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changer through the tube gauze vipe test fixture. Monitor before reentering the hot cell areato be sure that,the source is in the source changer. Remove the tube gauze and count

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vith scaler counting system. This assay must show no more

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than 0.005 pC1. If contamination is in excess of this h

level, the source is leaking and shall be rejected.

20.

Complete a Source Loading Log (Fi5ure II.2.1) for the operation.

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7-5 Revision 0 11 April 1980 1

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TECH /0PS MODEL 715 SHIPPING CONTAINER OPERATING INSTRUCTIONS Technical Data Size:

15.38 in, diameter, 23.88 in high (391mm diameter, 606mm high) 192 Capacity:

240 curies of Iridium as special form in con-junction with the Model 616 gamma ray projector 192 120 curies of Iridium as apscial form in con-junction with the Model 53), 713 and 644 gamma ray projectors Transport Status:

Type B USNRC USA /9039/B IAEA USA /9039/B(

)

General The Model 715 shipping container is designed as Type B packaging for the transport of the Tech / Ops Model 533, 616, 644 and 713 gamma ray projectors.

Receipt 1.

Upon receipt of the Model 715 shipping container, survey the package on all sides to ensure radiation levels do not exceed the following:

Surface 200 mR/hr At One Meter 10 mR/hr 2.

Check surface of. container for obvious damage.

3.

Chruk Invoice and Bill of Lading to ensure all are intact and are representative of the shipment.

4.

If there are any discrepancies in Items 1-3, secure the shipping container and contact Technical Operations, Inc. immediately to resolve the discrepancy.

(Tel: 800-225-7383, Telex 949313) 5.

If Items 1-3 are determined to be in order, place the shipping package in a restricted area until the gamma ray projector is to be unpacked.

7-6 Revision 0 11 April 1980

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Preparation for Shipment NOTE:

Personnel loading the Model 715 shipping container must have a calibrated and operational survey meter with a range of at least 0-1000 mR/hr. In addition, personnel monitoring devices must be worn during the operation.

They are,a film badge (or Thermolt.::inescent Dosimeter, TLD) and a direct reading pocket dosimeter.

1) Wearing a film badge and dosimeter, approach the gamma ray projector to be shipped with a calibrated and operable survey instrument.

2) Survey the exterior surf aces of the gamma ray projector to insure that the radiation intensities are normal. (Less than 50mR/hr at six inches from the surface)

Check to insure that the gamma ray projector is locked.

3) Insure that the proper molded filler is installed in the Model 715 for the projector which is to be transported. Also, insure that the

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insulation is in place.

1

4) Place the gamma ray projector in the Model 715 shipping container.

Place the top section of the molded filler over the projector.

Place the top section of the insulation in the container. Cover the container top with the gasket and lid.

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5) Place the clamp ring in place and tighten the bolt. Sealwire the bolt and nut using a tamperproof seal.

6) Survey the exterior surfaces of the container and insure that the maximum radiation level is less than 200 milliroentgens per hour.

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7) Measure the re.diation level three feet from all exterior surfaces of the container and insure that the radiation level is less than 10 milliroentgens per hour.

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8) Determine the proper shipping label to be applied to the package using Table I.

The maximwn radiation level measured three feet from any exterior surface of the shipping container is the Transport Index.

i 7-7 Revision 0 11 April 1980 x

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TABLE I o.

Maximum Radiation Levels Su r face 3 Feet 2

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N 0.5mR/hr None h

RADIDACTIVE s

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RADI0 ACTIVE-YELLOW II

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N 50mR/hr 1.0mR/hr RADIDACTIVENE >

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N 1

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N 200mR/hr

'10mR/hr

( s A010 ACTIVE:"vF 2

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7-8 Revision 0 11 April 1980 4

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9) Fill out the information requested on the label indicating:

a) Contents (Isotope) b)

No. of Curies c) Transport Index (Maximum Radiation Level measured at three feet from the surface)

10) Remove all old shipping labels. However, do not remove the metal container identification tag.

11) Affix new shipping labels to two opposite sides.

12) Properly complete the shipping papers indicating:

a) Proper shipping name (i.e. radioactive material, special form, n.o.s.)

9 b) Name of radionuclide (i.e.

Iridium) c) Physical or chemical form (or special form) d) Activity of Source (expressed in curies or millicuries) e) Category of label applied (i.e. radioactive Yellow II) f) Transport Index g) USNRC Identification Number (USA /9039/B) h) for export shipments, IAEA Identification Number (USA /9039/B)

Shipper's Certification required:

"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 applicable regulations of the Department of Transportation."

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 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 PRESCRIBED FOR CARGO-ONLY AIRCRAFT."

13) Return the Model 715 shipping container to:

Technical Operations, Inc.

40 North Avenue Burlington, MA 01803 Revision 0 USA 11 April 19.80 7-9

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8.

Acceptance Tests and Maintenance Program 8.1 Acceptance Tests 8.1.1 Visual Inspection The package is visually examined to assure that the appropriate fasteners are properly seal wired and that the package is properly marked.

Each gamma ray projector Models 533, 616, 644 and 713 to be shipped in the Model 715 container is also visually examined to assure that the appropriate fasteners are properly sealwired and that the package is properly labeled.

The seal weld of the radioactive source capsule is visually inspected for proper closure.

8.1.2 Structural and Pressure Tests The swage coupling between the source capsule and cable 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 subjected to a vacuum bubble leak test. The capsule is then subjected to a second wipe test for radioactive contamination. These tests are described in Section 7.4.

Failure of any of these tests will prevent use of this source assembly.

8.1.4 Component Tests i

The lock assembly of the Models 533, 616, 644 and 713 gamma ray projectors is tested to assure that the security of the radioactive source will be maintained. Failure of this test prevents use of the gamma ray projector until the lock assembly is corrected and retested. Only when the source assembly is correctly secure in the gamma ray projector is the Model 715 used as a shipping container.

8.1.5 Tests for Shielding Integrity The radiation levels at the surface of the package and at three feet from the surface are measured using a small detector survey instrument (i.e. AN/PDR-27). These radiation levels, when ex-l trapolated to the rated capacity of the package, must not exceed 200 milliroentgens per hour et the surface nor ten milliroentgens per hour at three feet from the surface of the package. Failure of this test will prevent use of the package.

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l 8-1 Revision 0

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11 April 1980 i

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i 8.1.6 Thermal Acceptance Tests Not Applicable 8.2 Maintenance Program y

8.2.1 Structural and Pressure Tests

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ry Not Applicable O

N 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 radioacrive contamination every six months.

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p' 8.2.3 Subsystem Maintenance I

The lock assembly of the gamma ray projectors is tested as described in Section 8.1.4, prior to each use of the Model 715 package.

I Additionally, the Model 715 package is inspected for tightness of fasteners, proper seal wires and general condition prior to each use.

i, 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 surface nor ten milliroentgens per hour at three feet from the surface.

p 8.2.6 Thermal D

Not Applicable 8.2.7 Miscellaneous

( E.

Inspections and tests designed for secondary users of this package under the general liccase provisions of 10CFR71.12(b) are included in Section 7.4.

8-2 Revision 0 11 April 1980 16032 I

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