ML20153B383

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Registry of Radioactive Sealed Sources & Devices,Safety Evaluation of Device for Models 5310,5310-1,5310-3 & 5310-5. Certificate:NR-582-D-803-B
ML20153B383
Person / Time
Issue date: 09/17/1998
From: Steven Baggett, John Lubinski
NRC
To:
Shared Package
ML20153B368 List:
References
SSD, NUDOCS 9809230092
Download: ML20153B383 (14)


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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY ~ EVALUATION OF DEVICE f

NO.: NR-582-D-803-B- DATE SEP 171998 PAGE 1 OF 12 DEVICE TYPE: Gamma. Gauge

'MODELSt 5310, 5310-1, 5310-3, 5310-5 MANUFACTURER /DISTRIBUTORe Lockheed Martin Tactical Systems '

Division

  • 459 Kennedy' Drive Archbald, PA'18403

-* Formerly Loral Control Systems ,

Weston Controls Division Fairchild Weston Systems, Inc.

Formerly Sangamo-Weston-Schlumberger SEALED SOURCE MODEL DESIGNATION: Amersham AMC.19 (5310,.5310-1) ,

DuPont Merck NER-479C.(5310, 5310-1)

Amersham AMC.30 (5310-3)

Amersham AMC.50 (5310-5)

ISOTOPE: MAXIMUM ACTIVITY: 1 Americium-241 1 Ci (37 GBq) (5310, 5310-1) ,

3 Ci (111 GBq) (5310-3) l 5 Ci (185 GBq) (5310-5)

T.RAK TEST FREOUENCY 6 months PRINCIPAL USE: (D) Gamma Gauges CUSTOM DEVICE: YES X NO 1

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE NO.: NR-582-D-803-B DATE: SEP 171998 EAGE 2 OF 12 DEVICE TYPEt Gamma Gauge DESCRIPTION:

The Models 5310, 5310-1, 5310-3 and 5310-5 source housings are similar in design and construction, and are designed to perform l thickness measurements of metals. Model 5310-1 was designed to '

replace Model 5310 and it allows for an optional Amersham 1 Ci (37 GBq) americium-241 sealed source. These devices are designed to be used in rolling mills or metal process lines. The source housing is attached to one arm of a "C" frame and a detector is l

attached to the opposite arm of the "C" frame.

P Model 5310 source housing consists of a 1 Ci (37 GBq) Amersham americium-241 sealed source (Model AMC.19), or a 1 Ci (37 GBq) ,

DuPont Merck americium-241 sealed source (Model NER 479-C), steel S

' source holder assembly, shutter mechanism, and steel housing. i The sides and bottom of the housing are sealed by welding and the  :

housing measures approximately 6" (15.24 cm) high by.6"  !

(15.24 cm) wide by 14" (35.56 cm) long. The cover contains a  !

1.375" (3.49 cm) diameter by .020" (5.08 mm) thick aluminum (or j optionally, beryllium) window. j l

Attached to the underside of the cover is a gasket, which allows )

the box to be hermetically sealed, and two holding brackets. The holding-bracket allows the cover to be locked to the housing through a key lock mechanism. This interlock system also- .

prevents the cover from being removed when the source is in the l "open" position. The cover is attached with lock nuts and tamper l

Eresistant bolts. Optionally, the box can be fitted with a water cooling system which circulates water through the frame. )

l The shutter mechanism consists of teflon slides, spring closed air cylinder, and a 0.5" (1.27 cm) stainless steel shutter. The ,

I piston is mounted along the axis of the housing and allows the shutter to be moved through teflon slides.

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4 REGISTRY OF' RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE

  • i NO.: NR-582-D-803-B DATE' PAGE 3 OF 12

$EP 171tN f

DEVICE TYPE: Gamma Gauge DESCRIPTION (Cont'd)-

i When the cylinder is engaged, the shutter slides toward the  !

piston allowing the radiation beam to pass through the window in  !

the cover. The opposite end of the piston shaft protrudes through  !

Eul opening in the housing indicating the source is in the "open" l position. If there is a pressure failure, a safety spring will j return the shutter to the closed position.

i The interlock system described above also locks the pis, ton from ,

engaging by covering the opening, thus, not allowing the shaft to -

protrude. Switches are located on each side of the teflon guide which send electrical signals to the shutter indicator. lights  :

located on'the mounting frame.  ;

I The source holder assembly consists of an outer lead shield, a  :

1.93" (4.90 cm) diameter cold rolled steel'(C.R.S.) cylinder,  !

spacer, C.R.S.-retainer, and an americium-241 sealed source. The  ;

cylinder has been machined to. accept the-sealed source. The source is held in place by a lead spacer placed behind the source ,

and then a retainer ring is bolted to the cylinder.

i The lead shield is bolted to the outside of the C.R.S. cylinder. }

A 0.375" ' (9.52 mm) diameter hole located in the source assembly j is aligned with the cylinder in the outer housing which allows  ;

wipe test' samples to be taken. The retainer attached to the  !

source assembly is bolted to the bottom of the source housing and '

is aligned with the window.

l A' threaded plug is located in the wall of the housing and allows wipe tests.to be taken of the source surface or at a location

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near the source on the source holder.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE NO.: NR-582-D-803-B DATE: SEP 1719H PAGE 4 OF 12 f

JDEVICE TYPE: Gamma Gauge I

DESCRIPTION (Cont'd)-

Models 5310-1, 5310-3 and 5310-5 differ slightly from the above design. Their source holder assemblies consist of a 3.25" (8.26 cm) diameter C.R.S. cylinder, stainless steel source holiar, lead spacer (shield) and a rectangular steel holder mounting plate. The C.R.S. cylinder is machined out to hold the stainless steel source holder which in turn holds the americium- l 241 sealed source. Models 5310-1, 5310-3 and 5310-5 differ only  ;

in the source installed and its corresponding source holder. )

Model 5310-1 contains a 1 Ci (37 GBq) americium-241 sealed source l l (1.18" [3.0 cm) diameter), Model 5310-3 contains a 3 Ci (111 GBq) j americium-241 sealed source (1.42" [3.60 cm] diameter) and Model  ;

5310-5 contains a 5 Ci (185 GBq) americium-241 sealed source (1.78" [4.52 cm] diameter).

' Air gaps between the aperture and detector are fixed and are from l 6 to 20" (15.24 to 50.8 cm) apart.

LABELING:

l A label is permanently attached to the side of the device and l l

states the isotope, activity, S/N, Model #, company logo, and the words " CAUTION RADIOACTIVE MATERIAL".

i A label is attached to the top of the device -and complies with j l the provisions of section 20.1901, 10 CFR Part 20. The label  !

l also contains the words " CAUTION RADIATION DEVICE".

For those devices under a general' license, the label complies with the provisions of section 32.51, 10 CFR Part 32 and contains j

, the following additional statements: l t

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES  ;

SAFETY EVALUATION OF DEVICE l

l NO.: NR-582-D-803-B DATE: $[p g7)ggg PAGE 5 OF 12  !

l DEVICE TYPEt Gamma Gauge I

LABELING (Cont'd)- I l

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" Gauge has legal requirements for testing source, l

shutter and indicators at six month intervals. Consult  ;

gauge manual for these and other required. procedures I and other legal obligations."

"The receipt, possession,.use and transfer of this device are subject to a general license or the equivalent and the regulations of the U.S. NRC or of a state with which the NRC has entered into an agreement for the exercise of regulatory authority. This label shall be maintained on the device in a legible condition. Removal of this label is prohibited."

DIAGRAMr

. See attachments 1 and.2.

CONDITIONS OF NORMAL USE:

The device is' subject to environmental conditions typically found l

in' rolling mills, or process lines for copper, steel, aluminum, or alloys at up to 300 F (148.89'C) at the outer surface with  :

internal water cooling of the housing. If there is no cooling  !

water flowing through the source housing the outer surface temperature will be controlled by administrated procedures so j that the temperature will not be permitted to exceed 150*F (65.56*C). i i

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. REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES .

SAFETY EVALUATION OF DEVICE >

4 NO.: NR-582-D-803-B DATE: SEP 1719N PAGE 6 OF 12 i

DEVICE TYPE: . Gamma Gauge PROTOTYPE TESTING:

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Sealed source Models AMC.19, AMC.30, AMC.50 and NER 479-C are i approved NRC sealed sources and have achieved ANSI N542-1977 j performance classifications of 77C64444, 77E64444, 77E64444 and 77C64444 respectively. ,

I The manufacturer claims that the gauges have been classified according to ANSI N538-1979 and have received ratings of ,

ANSI-64-885-885-R3 for Models $310, 5310-1, 5310-3 and -

-ANSI-64-785-785-R3 for Model 5310-5. '

A prototype of Model 5310 source housing was subjected to a penetration test according to 49 CFR.173.465 ~~(e) and-free drop (

test according to 49s CFR.173.465 (c) (1) . The welds were examined ,

and no visible damage was found.  !'

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Model'5310 has been in use by-both general.and specific licensees since 1977 - with. no reported incidents oft f ailure.

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EXTERNAL RADIATION LEVELS:

l The manufacturer reports the maximum external' radiation levels, l outside.the direct beam path, for Models 5310, 5310-1, 5310-3 and  !

5310-5.when loaded with maximum activity are the following: l Measured radiation i Distance levels (mrem /hr) '

U Models Model 5310. 5310-1 and 5310-3 5310 l 5-cm. (1.97") 0.6 1.5-30 cm (11.81"): <0.1 0.3 100 cm: (39.37")

-Background Background l_

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE ,

NO.: NR-582-D-803-B DATE: gp PAGE 7 OF 12 DEVICE TYPE: Gamma Gauge QUALITY ASSURANCE AND CONTROL: l Loral Control Systems has supplied a quality assurance and  !

control program which has been deemed acceptable for licensing i purposes by the NRC. A copy of this program is on file with the NRC. The assurance and control program consist of the following ,

basic components: ,

  • In-process Inspection I
  • Assembly Inspection  !
  • Receiving Inspection  !
  • Structural Welding
  • Processing Rejected Material  ;

LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:  ;

  • Devices intended for distribution to persons j specifically licensed by the NRC or an Agreement State , ;

shall be labeled in accordance with Section 20.1901 of ]

10 CFR Part 20. 1 I

  • Devices intended for distribution to persons generally.

licensed pursuant to Section 31.5 of 10 CFR Part 31 shall be labeled in accordance with Section 32.51(a) (3) of 10 CFR Part 32.

  • Devices intended for use under a general license shall be installed and initially tested for proper operation l of the source exposure mechanism, safety warning
j. components, labels, cooling system (if used), external radiation levels and leak tested by Loral Control Systems, or other persons specifically licensed by the NRC or an Agreement State.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE i

NO.: NR-582-D-803-B DATE: SEP 171998 PAGE 8 OF 12 1

DEVICE TYPE: Gamma Gauge LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE (Cont'd):

  • Handling, Storage, Use, Transfer, and Disposal: For devices used under specific license to be determined by the licensing authority. If cooling system is used procedures and warnings to indicate if the water volume is below 1 gallon per minute should be required. For devices used under general license to be covered by the requirements of 10 CFk 31.5.
  • The device shall be leak tested at 6 month intervals using techniques capable of detecting 0.005 microcurie (185 Bq) of removable contamination. The test shall be performed by Loral Control Systems, or other persons specifically licensed.
  • This registration sheet and the information contained with the references shall not be changed without the written consent of the NRC.

SAFETY ANALYSIS

SUMMARY

Since the effective date of this document, the Models 5310, 5310-1, 5310-3 and 5310-5 are not current products manufactured by the Lockheed Martin. The total number of products still in use are 425. The distributor had ceased all activities related to the manufacturing, sale, and distribution of this device.

The devices were used to determine the thickness of copper, steel, aluminum, or alloys. The radioactive source is contained within a C.R.S. cylinder located inside a steel housing. A pneumatic operated piston attached to the shutter controls the radiation beam.

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE NO.: NR-582-D-803-B DATE. SEP 171998 PAGE 9 0F 12 DEVICE TYPE- Gamma Gauge SAFETY ANALYSIS

SUMMARY

(Cont'd)-

When the shutter is in the "open" position, the primary beam exits the housing, is reduced in intensity by the material undergoing measurement, and strikes the detector measuring system. The output of the measuring system is used for material evaluation / control.

The gamma sources used in Models 5310, 5310-1, 5310-3, and 5310-5 have received ANSI N542-1977 classifications of 77C64444, 77C64444, 77E64444, and 77E64444 respectively. The devices have received ANSI N538-1979 ratings of ANSI-64-885-885-R3 for Models 5310, 5310-1, 5310-3 and ANSI-64-785-785-R3 for Model 5310-5.

This indicates that normal and accident conditions of use are highly unlikely to cause breach of containment integrity. During use, the source is sealed within the housing such that the source is protected against possible airborne corrosive and other types of contaminants. Even if the capsule developed a defect (hole or crack), leakage of radioactive material would be highly unlikely l because the americium-241 is in non-dispersible ceramic form.

l The distributor has submitted sufficient information to provide reasonable assurance that:

  • The device can be safely operated by persons not having training in radiological protection.

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  • Under ordinary conditions of handling, storage, and use of the device, the byproduct material contained in the device will not be released or inadvertently removed from the device, and it is unlikely that any person will receive in any period of one calendar quarter a dose in excess of 10 percent of the limits specified in the table in Section 20.1201(a), 10 CFR 20.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE NO.: NR-582-D-803-B DATE: SEP 1719N PAGE 10 OF 12 '

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DEVICE TYPEt Gamma Gauge  !

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SAFETY ANALYSIS

SUMMARY

(Cont'd)-

e Under accident conditions (such as fire and explosion) j associated with handling, storage, and use of the' device, it is unlikely that any person would receive an 3 external radiation dose or dose commitment in excess of  :

the dose to the appropriate organ as specified in the  !

following chart: )

i PART OF BODY rem /mSv  !

i Whole body; head and trunk; {

active blood-forming organs; j

gonads; or. lens of eye 15/150 'j Hands and forearms; feet and -f ankles; localized areas of skin I averaged over areas no larger.

than'1'cm2- (0.16 in2). 200/2000 j Other organs 50/500  !

Operation of-the shutter is controlled by a key lock. This same l locking: system discourages unauthorized access to the source. j The device will be used in industrial environments; however, j thesecenvironments are not expected to be severe because of the need to protect the detection system. In the event of a fire, breach of containment integrity of'the radioactive source is z

unlikely. Prototype evaluation of the source shows it to be adequate to withstand a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 800*C (1,472*F) fire.

-Protection provided by the device housing further assures radioactive material containment in the event of an accident.

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l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES j SAFETY EVALUATION OF DEVICE l 1

NO.: NR-582-D-803-B DATE: $[p 3 7 jggg PAGE 11 OF 12 l

DEVICE TYPE: Gamma Gauge i SAFETY ANALYSIS

SUMMARY

(Cont'd)-

l Based on the above and the information referenced below, we  !

conclude that Loral Control Systems Models 5310, 5310-1, 5310-3 and 5310-5 source housings are acceptable for distribution to specific and general licensees. Further, we conclude that the source housings can be expected to maintain their containment  !

integrity adequately for normal conditions of use and for i accidental conditions that might occur during use.  !

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REFERENCES:

The distributor has submitted the following supporting documents  !

which are hereby incorporated by reference and are made a part of  ;

-this registration document- '

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  • Lockheed Martin's letters dated April 24, 1981, January 26, 1981, July 16, 1980, September 27, 1979, ,

September 1, 1978, November 23, 1976, September 29, l

1976, June 7, 1976, March 11, 1976, July 18, 1988, July 14, 1988, July 12, 1988, May 15, 1? . L , j November 14, 1991 and January 10, 1992, with enclosures  !

thereto.  !

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  • Lockheed Martin's letter dated September 23, 1997, t

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t REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE l

NO.: NR-582-D-803-B DATE: g[p j 7 gggg PAGE 12 OF 12 l

. DEVICE TYPEe Gamma Gauge- }

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REFERENCES (Cont'd)- -

  • Tremont Tech-Writers' letters dated March 27, 1998.

l ISSUING AGENCYr ,

t U..S. Nuclear Regulatory' Commission i t

Date:

SEP 171888 Reviewer: #

//p4 ,

ohn W. Lubinski i I '

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Date: SEP l 719td Concurrence: M '

Iteven L. Baggett  !

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i REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE l f C NR-582-D-803-B DATE- ATTACHMENT 1

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