ML20154M805
| ML20154M805 | |
| Person / Time | |
|---|---|
| Issue date: | 10/19/1998 |
| From: | Steven Baggett, John Lubinski NRC |
| To: | |
| Shared Package | |
| ML20154M744 | List: |
| References | |
| SSD, NUDOCS 9810210038 | |
| Download: ML20154M805 (12) | |
Text
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i REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
'l NO.: 'NR-582-D-803-B DATE:
PAGE 1 OF 10 gjt DEVICE TYPE:
Gamma Gauge b
MODELS:
5310, 5310-1, 5310-3, 5310-5 l
i MANUFACTURER / DISTRIBUTOR:
Lockheed Martin Tactical Systems Division
- 459 Kennedy Drive i
Archbald, PA 18403 i
- Formerly Loral Control Systems j
Weston Controls Division Fairchild Weston Systems, Inc.,
Formerly Sangamo.-Weston-l Schlumberger SEALED SOURCE MODEL DESIGNATION:
Amersham AMC.19 (5310, 5310-1)
DuPont Merck NER-479C (5310, j
5310-1)
Amersham AMC.30 (5310-3)
Amersham AMC.50 (5310-5) j ISOTOPE 1 MAXIMUM ACTIVITY:
Americium-241-1 Ci (37 GBq) (5310, 5310-1) 3 Ci (111 GBq) (5310-3) 5 Ci (185'GBq) (5310-5) 1 i
i
. LEAK' TEST FREQUENCY:
6 months PRINCIPAL USE:
(D)
Gamma Gauges CUSTOM' DEVICE:
YES X
NO l
9910210038 981016 PDR RC SSD PDR L
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY) i i
NO.:
NR-582-D-803-B.
DATE: OCT 19 NES PAGE 2 OF 10 DEVICE TYPE:
Gamma Gauge j
lu DESCRIPTION:
l l
The Models 5310, 5310-1, 5310-3'and 5310-5 source housings are L
similar in design and construction, and are designed to perform l
thickness measurements of metals.
Model 5310-1 was designed to 1
l replace Model 5310 and it allows for an optional Amersham 1 Ci L
(37 GBq) amer cium-241 sealed source.
These devices are designed d
L to'be used in rolling mills-or metal process. lines.
The source i
housing is attached to one arm of a "C"
frame and a detector is j
attached to the opposite arm of the "C" frame.
l 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 source holder assembly, shutter mechanism,'and steel housing.
The sides and, bottom of the housing are sealed by welding and the
. housing measures =approximately 6" (15.24 cm) high by 6" i
(15.24 cm) wide by 14" (35.56 cm) long.
The cover contains a i
1.375" (3.49 cm). diameter by.020" (5.08 mm) thick aluminum (or optionally,' beryllium) window.
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 "open" position..The cover is attached with lock nuts and tamper
-resistant bolts.
Optionally, the box can be fitted with a water cooling system which circulates water through the frame.
The shutter m'.hanism consists of teflon slides, spring closed
-air cylinder, and a 0.5" (1.27 cm) stainless steel shutter.
The pioton is mounted along the axis of the housing and allows the shu'eter to be moved through teflon slides.
When the cylinder is engaged, the shutter slides toward the l
l l
piston allowing the radiation beam to pass through the window in j
l the cov.ir. The opposite end-of the piston shaft protrudes through j
~
i l
an open.ng.in the housing indicating the source is in the "open" position.
If there is a pressure failure, a safety spring will i
return t he shutter to the closed position.
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
001 19 198 PAGE 3 OF 10 DEVICE TYPE:
Gamma Gauge DESCRIPTION (Cont'd):
The interlock system described above also locks the piston 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.
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.
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 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.
A threaded plug is locatec in the wall of the housing and allows wipe tests to be taken of the source surface or at a location I
near the source on the source holder.
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 holder, lead spacer (shield) and a rectangular steel holder l
mounting plate. The C.R.S.
cylinder is machined out to hold the stainless steel source holder which in turn holds the americium-241 sealed source.
Models 5310-1, 5310-3 and 5310-5 differ only in the source installed and its corresponding source holder.
l Model 5310-1 contains a 1 Ci (37 GBq) americium-241 sealed source (1.18" [3.0 cm] diameter), Model 5310-3 contains a 3 Ci (111 GBq) 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).
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES l
SAFETY EVALUATION OF DEVICE i
l (ANENDED IN ITS~ENTIRTY)
L l
NO.:
NR-582-D-803-B DATE:
Sci 19438 PAGE'4 OF 10 i
DEVICE TYPE:
Gamma Gauge DESCRIPTION (Cont'd):
Air gaps between the aperture and detector are fixed and are from 6'to 20" (15.24 to 50.8 cm) apart, j
?
LABELING:
A label is permanentlylattached to the side of the device and states the isotope, activity, S/N, Model #, company logo, ar.d the words " CAUTION RADIOACTIVE MATERIAL".
A label is-attached to the. top of the device'and complies with the' provisions of section 20.1901,' 10 CFR Part'20.
The label also contains.the words " CAUTION RADIATION DEVICE".
For-those devices under~a general license, the label complies j
with the provisions-of section:32.51, 10 CFR Part 32 and contains the following addition'listatements:
I a
" Gauge hasilegal requirements for testing source, shutter-and indicators at six' month intervals.
Consult gauge manual 1for these~and other required procedures and other lega1' 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 Jabel shall be maintained on the device in a legible condition.
Removal-of this label is prohibited."
DIAGRAM:
See attachments ] and 2.
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REGISTRYLOF RADIOACTIVE SEALED. SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (ANENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: gy j g gg PAGE 5 OF 10-DEVICE TYPE:
Gamma Gauge 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 l
temperature will be controlled by administrated procedures so
-that the temperature will'not be permitted to exceed 150*F (65.56 C).
PROTOTYPE TESTING:
Sealed source Models AMC.19, AMC.30, AMC.50 and NER 479-C are approved NRC sealed sources and have achieved ANSI N542-1977 performance classifications of 77C64444, 77E64444, 77E64444 and 77C64444 respectively.
-The manufacturer claims that the gauges have been classified according to ANSI N538-1979 and have received ratings of I
ANSI-64-885-885-R3 for Models 5310, 5310-1, 5310-3 and ANSI-64-785-785-R3 for Model 5310-5.
l 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 49 CFR 173.465 (c) (1).
The welds were examined
'and no visible damage was found.
~
Model 5310 has been in use by-both' general and specific lic_asees
]
since 1977 with'no reported' incidents of failure.
EXTERNAL RADIATION LEVELS:
The manufacturer reports the maximt. external radiation levels, outside the direct beam path, for Models 5310, 5310-1, 5310-3 and l
i l
5310-5 when loaded with maximum activity are the following:
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE-(AMENDED IN ITS ENTIRTY) l RNO.:
NR-582-D-803-B DATE: gy j g Jgg PAGE 6 OF 10
{
-DEVICE TYPE:
Gamma Gauge-
]
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EXTERNAL RADIATION LEVELS (Cont'd):
l Measured radiation Distance levels (mrem /hr)
Models Model 5310, 5310-1 and 5310-3 5310-5 5 cm (1.97")
0.6 1.5 30 cm (11.81")
=<0.1 0.3 100 cm (39.37")'
Background
Background QUALITY ASSURANCE AND CONTROL:
Loral Control Systems has supplied a quality assurance and i
control program which has been deemed acceptable for licensing
-l purposes by the NRC. A copy of this program is on file with the j
NRC.
The assurance and' control program consist of the following-basic components:
t In-process Inspection j
Assembly Inspection Receiving Inspection
. Structural' Welding Processing Rejected Material' l
l LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:
Devices intended for distribution to persons specifically licensed by the NRC or an Agreement State shall be labeled in accordance with Section 20.1901 of 10 CFR Part 20.
= Devices intended for distribution to persons generally licensed pursuant to Section 31.5 of 10 CFR Part 31 t
L shall be labeled in accordance with Section 32.51(a) (3)_
l of 10 CFR Part 32.
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES l
SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: RT I S lag PAGE 7 OF 10 DEVICE TYPE:
Gamma Gauge LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE (Cont'd):
l Devices intended for use under a general license shall l
be installed and initially tested for proper operation l
of the source exposure mechanism, safety warning l
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.
Handling, Storage, Use, Transfer, and Disposal:
For devices used under specific license to be determined by i
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 CFR 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 and indicated that servicing to existing products would be performed by Honeywell-Measurex DMC Corporation'.
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r REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: OCT 1918N PAGE 8 OF 10
-DEVICE TYPE.:
Gamma Gauge j
l l
SAFETY ANALYSIS
SUMMARY
(Cont'd):
l l
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.
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.,
L The gamma sources used'in Models 5310,-5310-l',-5310-3, and 5310-5 L
have received ANSI N542-1977 classifications of 77C64444, l
'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 l
highly;unlikely to cause breach of containment integrity.
During j
l use, the source is^ sealed within the housing such that the source l
l is protected against possible airborne corrosive and other types l=
of contaminants.
Even if the capsule developed a defect (hole or crack),fleakage of. radioactive materia 1'would be highly unlikely because the americium-241 is in non-dispersible ceramic form.
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, l
Under ordinary conditions of handling, storage, and use f-
=
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 (AMENDED IN ITS ENTIRTY)
NO.: 'NR-582-D-803-B DATE:
ElI ll NUl PAGE 9 OF 10 DEVICE' TYPE:
Gamma Gauge
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' SAFETY ANALYSIS
SUMMARY
'(Cont'd):
i Under accidentLconditions (such as! fire and explosion) associated with handling, storage, and use of the device, it is unlikely that any person would receive an external radiation dose or dose commitment in excess of the dose to the appropriate organ as specified in the following chart:
PART OF BODY.
rem /mSv Whole body; head and trunk; active blood-forming organs; gonads; or lens of eye 15/150 Hands and forearms; feet and ankles; localized areas of skin averaged.over areas no larger than l'cm2 (0.16 in2) 200/2000 OtherLorgans 50/500 Operation'of the shutter is controlled by a key lock.
This same locking system discourages unauthorized access to the source.
The device will be used in industrial environments; however, these environments are'n'ot. expected to be severe because of the need tol protect the detection system,-
In the event of a fire, breach of containment integrity of the radioactive source is unlikely.
Prototype ~ evaluation of the source shows it to be adequate to withstand-a'l hour, 800 C (1,472fF) fire.
Protection provided by the device. housing further assures
~
radioactive material containment in the event of an accident.
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 l
source housings canLbe expected to maintain their containment l
. integrity adequately for normal conditions of use' and for I
accidental conditions that might occur during use.
6 h
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h REGISTRY OF. RADIOACTIVE SEALED SOURCES AND DEVICES
' SAFETY' EVALUATION OF DEVICE l
(AMENDED IN ITS ENTIRTY) l
. NO. : ' NR-582-D-803-B DATE: SCT 1 s 13 PAGE 10 OF 10 3
DEVICE TYPE:
Gamma Gauge l
REFERENCES:
i The distributor has submitted the following supporting documents which are hereby incorporated by reference and are made a part of this registration document:
l 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, 7
1976,~ June 7, 1976, March 11, 1976, July 18, 1988, July;14,.1988, July 12, 1988, May 15, 1991, November 14, 1991 and January 10,-1992, with enclosures l-thereto.
Lockheed Martins letter. dated September 23,.1997.
~
i Tremont Tech-Writers' letters = dated March 27, 1998.
ISSUING AGENCY:
l
-U.S.
Nuclear Regulatory Commissi~on.
-[
Date:
OCIl'8IIII Reviewer:
J nn W.
Lubinski f'
NT191991
.Date-Concurrence: 8 Mo" e
~It!even L.
Baggett L
I-i i.
I REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE sAMENDED IN ITS ENTIRTY) 0C119 bSI NO.: NR-582-D-803-B DATE:
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY) i 1
NO.: NR-582-D-803-B DATE:
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i REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.- NR-582-D-803-B DATE:
00I I O ATTACHMENT 2 l
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. Source Source 5310,1(original) 5310-1 5510-5
& 5310-5 3
SKETCH SF
'ING CROSS SECTION OF SOURCE "H0l_ DER ASSEMBLIES" e
I October 16, 1998 l
Mr. Tim Foley Director, Manufacturing Services Lockheed Martin Tactical Systems Division 459 Kennedy Drive Archbald, PA 18403-1598 l
Dear Mr. Foley:
Based on the discussion with Mr. Robert Pazzaglia, Radiation Safety Officer, on October 6,1998 we have amended registration certificate NR-582 D-803-B to reflect that the servicing to existing devices would be performed by Honeywell-Measurex DMC Corporation.
Please review the registration certificate (copy enclosed) in its entirety and notify us immediately if there are any errors or omissions, if you have any questions call me at (301) 415-5787 or Mr. Steven Baggatt at (301) 415-7273.
Sincerely,
/s/
Seung J. Lee, Mechanical Engineer j
Materials Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS
Enclosure:
As stated l
cc w/ encl: SKimberley, LFDCB j
Distribution:
a MSB r/f NMSS r/f SSD-97-61 NE01 SSD File # NR-582-D-803-B DOCUMENT NAME: C:\\SJL\\NR582803.CP2 7a receNo e cop ' of INe document, Indicate in the box: "C" = Copy hthout attachent/ enclosure "_E's Cop f with attachment / enclosure "N". No copy OFFICE MSB lE MSB M lM l
l NAME SLee cif JLubinsla DATE 10/15/98 10Av/98 OFFICIAL RECORD COPY j
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
PAGE 1 OF 10 NO.:
NR-582-D-803-B DATE:
OCT 10 DEVICE TYPE:
Gamma Gauge MODELS:
5310, 5310-1, 5310-3, 5310-5 MANUFACTURER / DISTRIBUTOR:
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 1
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:
Americium-241 1 Ci (37 GBq) (5310, 5310-1) 3 Ci (111 GBq) (5310-3) 5 Ci (185 GBq) (5310-5)
LEAK TEST FREQUENCY:
6 months PRINCIPAL USE:
(D)
Gamma Gauges l
CUSTOM DEVICE:
YES X
NO l
[ic r ^ ^ f n,A 77, n e p -_
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
0011919N PAGE 2 OF 10 DEVICE TYPE:
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 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 attached to the opposite arm of the "C"
frame.
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 americiam-241 sealed source (Model NER 479-C), steel source holder assembly, shutter mechanism, and steel housing.
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 optionally, beryllium) window.
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 "open" position.
The cover is attached with lock nuts and tamper resistant bolts.
Optionally, the box can be fitted with a water cooling system which circulates water through the frame.
The shutter mechanism consists of teflon slides, spring closed air cylinder, and a 0.5" (1.27 cm) stainless steel shutter.
The piston is mounted along the axis of the housing and allows the shutter to be moved through teflon slides.
l 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 an opening in the housing indicating the source is in the "open" position.
If there is a pressure failure, a safety spring wil; return the shutter to the closed position.
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
0011914' PAGE 3 OF 10 DEVICE TYPE:
Gamma Gauge DESCRIPTION (Cont'd):
The interlock system described above also locks the piston 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.
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.
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 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.
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 near the source on the source holder.
Models 5310-1, 5310-3 and 5310-5 differ slightly from the above e
design.
Their source holder assemblies consist of a 3.25" (8.26 cm) diameter C.R.S.
cylinder, stainless steel source holder, 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-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 (1.18" [3.0 cm) diameter), Model 5310-3 contains a 3 Ci (111 GBq) 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).
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_ _ _. _. ~.. _ _-- __
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l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES L
SAFETY EVALUATION OF DEVICE i
(AMENDED IN ITS ENTIRTY)
I l
NO.:
NR-582-D-803-B DATE:
K119150 PAGE 4 OF 10 i
DEVICE TYPE:
Gamma Gauge
{
l DESCRIPTION. (Cont'd):
r i
L Air gaps between the aperture and detector are fixed and are from 6 to 20" (15.24 to 50.8 cm) apart.
LABELING:
A label is permanently attached to the side of the device and 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 the provisions of section 20.1901, 10 CFR Part 20.
The label 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 the following additional statements:
" Gauge.has legal requirements for testing source, i
shutter and indicators at six month intervals.
Consult gauge manual for these and other required procedures 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 35 prohibited."
l DIAGRAM:
L See attachments 1 and 2.
i 1
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (ANENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: ggy }g ygg PAGE 5 OF 10 DEVICE' TYPE:
Gamma Gauge CONDITIONS OF NORMAL USE:
The. device is subject to environmental conditions typically found 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 that the temperature will not be permitted to exceed 150 F (65.56 C).
PROTOTYPE TESTING:
Sealed source Models AMC.19, AMC.30, AMC.50 and NER 479-C are approved-NRC sealed sources and have achieved ANSI N542-1977 performance classifications of 77C64444, 77E64444, 77E64444 and 77C64444 respectively.
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 5310, 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 49 CFR 173.465 (c) (1).
The welds were examined and no visible damage was found.
Model 5310 has been in use by both general and specific licensees since 1977 with no reported incidents of failure.
EXTERNAL RADIATION LEVELS:
(:
l The manufacturer reports the maximam 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:
i 1
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: g jg]g PAGE 6 OF 10 DEVICE TYPE:
Gamma Gauge EXTERNAL RADIATION LEVELS (Cont'd):
Measured radiation Distance levels (mrem /hr)
]
Models Model 5310, 5310-1 and 5310-3 5310-5 5 cm (1.97")
0.6 1.5 30 cm (11.81")
<0.1 0.3 100 cm (39.37")
Background
Background QUALITY ASSURANCE AND CONTROL:
Loral Control Systems has supplied a quality assurance and control program which has been deemed acceptable for licensing 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 Assembly' Inspection Receiving Inspection I
Structural Welding Processing Rejected Material LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:
Devices intended for distribution to persons specifically licensed by the NRC or an Agreement State al be lab d in accordance with Section 20.1901 of l
l Devices intended for distribution to persons generally l'
licensed pursuant to Section 31.5 of 10 CFR Part 31 L
shall be labeled in accordance with Section 32.51(a) (3) of 10 CFR Part 32.
1 i
l i
i i
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l l
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES l
SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: g} j g 198 PAGE 7 OF 10 DEVICE TYPE:
Gamma Gauge LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE (Cont'd):
Devices intended for use under a general license shall be installed and initially tested for proper operation of the source exposure mechanism, safety warning 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.
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 sheald be required.
For devices used under general license to be covered by the requirements of 10 CFR 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 and indicated that servicing to existing products would be performed by Honeywell-Measurex DMC Corporation.
l l
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l i
I REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES j
SAFETY EVALUATION OF PEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: RT 19 IH8 PAGE 8 OF 10 DEVICE TYPE:
Gamma Gauge SAFETY ANALYSIS
SUMMARY
(Cont'd):
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.
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 AMSI 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-64-785-78 R3 for Model 5310-5.
This indicates that normal and accidert 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 because the americium-241 is in non-dispersible ceramic form.
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.
Under ordinary conditions of handling, storage, and use of the device, the byproduct material contained in the l
device will not be released or inadvertently removed from the device, and it is unlikely that any person l
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.
~
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (A9 ENDED IN ITS ENTIRTY) l 1
. NO.:
NR-582-D-803-B DATE:
$519 $N PAGE 9 OF 10 DEVICE TYPE:
' Gamma Gauge SAFETY ANALYSIS
SUMMARY
(Cont'd):
Under accident conditions (such as fire and explosion) associated with handling, storage, and use of the device, it is unlikely that any person would receive an external radiation dose or dose commitment in excess of the dose to the appropriate organ as specified in the i
following chart:
i PART OF BODY
-rem /mSv
~ Whole body; head and trunk; active blood-forming organs; gonads; or lens of eye 15/150 Hands and forearms; feet and l
ankles; localized areas of skin averaged over areas no larger than 1 cm2 (0.16 in2) 200/2000 Other organs 50/500 Operation of the shutter is controlled by a key lock.
This same
- locking system discourages unauthorized access to the source, The device will be used in industrial environments; however, o
l these environments 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 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.
l Protection'provided by the device housing further assures radioactive material containment in the event of an accident.
Based on the above and the information referenced below, we L
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 accidental conditions that might occur during use.
i 2
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE I
(AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: OCi 19 33 PAGE 10 OF 10
' DEVICE TYPE:
Gamma Gauge i
REFERENCES:
The distributor has submitted the following supporting documents which are hereby incorporated by reference and are made a part of this registration document:
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, 1976, June 7, 1976, March 11, 1976, July 18, 1988, j
July 14, 1988, July 12, 1988, May 15, 1991, November 14, 1991 and January 10, 1992, with enclosures thereto.
j l
Lockheed Martin's letter dated September 23, 1997.
Tremont Tech-Writers letters dated March 27, 1998.
i ISSUING AGENCY:
U.S. Nuclear Regulatory Commission i
/
I Date:
SCI l'9 E Reviewer:
i J 6n W.
Lubinski M
Date:
Concurrence: -
$deven L.
Baggett i
4
l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY) i 1
NO.
NR-582-D-803-B DATE:
0C1191930 ATTACHMENT 1
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY) 1 NO.: NR-582-D-803-B DATE:
00I I O ATTACHMENT 2 i
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VIIIIIIInIIIIL TA T T T a n s H Ki U Hlull IIIIIIIII, n:,,',
- ,7 '11 IIIII b Source
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Source 5310,.i(original) 5310-1 5 510-5 s 5310-5 3
SKETCH SHOWING CROSS SECTION OF SOURCE " HOLDER ASSEPBLIES" o
October 16, 1998 Mr. Tim Foley Director, Manufacturing Services Lockheed Martin Tactical Systems Division 459 Kennedy Drive Archbald, PA 18403-1598 1
Dear Mr. Foley:
Based on the discussion with Mr. Robert Pazzaglia, Radiation Safety Officer, on October 6,1998 l
l we have amended registration certificate NR-582-D-803-B to reflect that the servicing to existing l
device; would be performed by Honeywell-Measurex DMC Corporation.
Please review the registration certificate (copy enclosed) in its entirety and notify us immediately if there are any errors or omissions.
If you have any questions call me at (301) 415-5787 or Mr. Steven Baggett at (301) 415-7273.
Sincerely,
/s/
Seung J. Lee, Mechanical Engineer Materials Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS l
Enclosure:
As stated cc w/ encl: SKimberley, LFDCB Distribution:
MSB r/f NMSS r/f SSD-97-61 NE01 SSD Filo # NR-582-D-803-B i
DOCUMENT NAME: C:\\SJL\\NR582803.CP2 T a receive a cop i of this document. Indicate in the box: "C" = Copy hthout attacknent/ enclosure 'E' = Copy with attachmer*Venclosure
'N' = No copy OFFICE MSB lE MSB _M lAl l
l l
j tif JLubinsid NAME SLee DATE 10/15/98 10Av/98 OFFICIAL RECORD COPY I
i 4
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' REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
--t sana PAGE 1 OF 10 OCTIh1W{
DEVICE TYPE:
Gamma Gauge MODELS:
5310,.5310-1, 5310-3, 5310-5 MANUFACTURER / DISTRIBUTOR:
Lockheed Martin Tactical Systems L.
Division
- l 459 Kennedy Drive l,
Archbald, PA 18403
- Formerly Loral. Control Systems Weston Controls Division Fairchild Weston Systems, Inc.
Formerly Sangamo-Weston-Schlumberger j
i i
l_
SEALED SOURCE MODEL DESIGNATION:
Amersham AMC.19 (5310, 5310-1) l DuPont Merck NER-479C (5310, 5310-1)
Amersham AMC.30 (5310-3) i Amersham AMC.50 (5310-5)
. ISOTOPE:
MAXIMUM ACTIVITY:
Americium-241 1 Ci (37 GBq) (5310, 5310-1) 3 Ci (111 GBq) (5310-3) 5 Ci (185 GBq) (5310-5)
LEAK TEST FREQUENCY:
6 months PRINCIPAL-USE:
(D)
Gamma Gnuges CUSTOM DEVICE:
'i ES X
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i REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES s
L SAFETY EVALUATION OF DEVICE (AMENDED IN'ITS ENTIRTY)
)
NO.:
NR-582-D-803-B DATE: 0C119 HWB PAGE 2 OF 10 j
DEVICE TYPE:
Gamma Gauge 1
DESCRIPTION:
The Models 5310, 5310-1, 5310-3 and 5310-5 source housings are l
similar in design and. construction, and are designed to perform i
L thickness measurements of metals.
Model'5310-1 was designed to l
replace Model 5310 and it allows for an op'tional Amersham 1 Ci L
'(37 GBq) americium-241 sealed source. 'These devices are designed I
to be used in rolling mills or metal process lines.
The source l
housing is attached to one arm of a "C" frame and a detector is attached to the opposite arm of the "C"
frame.
l 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) l DuPont Merck americium-241 sealed source (Model NER 479-C), steel L
-source holder assembly, shutter mechanism, and steel housing.
L The sides and bottom of the housing are sealed by welding and the i
housing measures approximately 6" (15.24 cm)-high by 6" l
(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 optionally, beryllium) window.
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 i
through a key lock mechanism. -This interlock system also i
prevents the cover from being removed when the source is in the "open" position.
The cover is attached with lock nuts and tamper resistant bolts.
Optionally, the box cat 4 be fitted with a water cooling system which circulates water through the frame.
The. shutter mechanism consists of teflon slides, spring closed L
air cylinder,-and a 0.5" (1.27 cm) stainless steel shutter.
The piston.is mounted along the axis of the housing and allows the shutter to be moved through teflon slides.
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 an opening in the housing indicating the sotwee is in the "open" i:
position.
If there is a pressure failure, a safety spring will return the shutter to the closed position.
i
- -. _ _ _. _.. ~. __ _ _ _ - _ _.. _ __ _ _ _ _ _. _._.__.. _ _. _ _
i i
t l
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES l
l SAFETY EVALUATION OF DEVICE
[
(AMENDED IN ITS ENTIRTY) i l
NR-582-D-803-B DATE:
OCil9UNO PAGE 3 OF 10 NO,:
L DEVICE TYPE:
Gamma Gauge I
f L
l j
DESCRIPTION (Cont'd):
The interlock system described above also locks the piston 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 i
-located on the mounting frame.
l The source holder assembly consists of an outer lead shield, a l
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 L
source is held in place by a lead spacer placed behind the source and then a retainer ring is bolted to the cylinder.
l l
The lead shield is bolted to the outside of the C.R.S.
cylinder.
l A 0.375" (9.52 mm) diameter hole located in the source assembly l
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.
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 l
I near the source on the source holder.
l l
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 j.
holder, 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-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 (1.18" [3.0 cm) diameter), Model 5310-3 contains a 3 Ci (111 GBq) 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),
i l
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE 5
(AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
001 1 9 150 PAGE 4 OF 10 DEVICE TYPE:
Gamma Gauge DESCRIPTION (Cont'd):
Air gaps between the aperture'and detector are fixed and are from 6 to 20" (15.24 to 50.8 cm) apart.
l LABELING:
]
A label is permanently attached to the side of the device and states the isotope, activity, S/N, Model #,
company logo, and the words " CAUTION RADIOACTIVE MATERIAL".
A label is attached to the top of the device and complies with the provisions of section 20.1901, 10 CFR Part 20.
The label.
also contains the words " CAUTION RADIATION DEVICE".
For those devices under a general license, the label complies with~the provisions of section 32.5' 10 CFR Part 32 and contains the following additional statements:
" Gauge has legal requirements for testing source, shutter and indicators at six month intervals.
Consult gauge manual for these and other required procedures 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 i
for the exercise of regulatory authority.
This label shall be maintained on the device in a legible condition.
Removal of this label is prohibited."
DIAGRAM:
1 J
See attachments 1 and 2.
i
--~=
=_- -
i l
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE i
(AMENDED IN ITS ENTIRTY)
I
'NO.:
NR-582-D-803-B DATE: ggy;gygg PAGE 5 OF 10 DEVICE TYPE:
Gamma Gauge CONDITIONS OF NORMAL USE:
l 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 that the temperature will not be permitted to exceed 150 F (65.56"C).
j i
b PROTOTYPE TESTING:
Sealed source Models AMC.19, AMC.30, AMC.50 and NER 479-C are approved NRC sealed sources and have achieved ANSI N542-1977 i
i performance classifications of 77C64444, 77E64444, 77E64444 and i
77C64444 respectively.
The manufacturer claims that the gauges have been classified according to ANSI N538-1979 and have received ratings of l
ANSI-64-885-885-R3 for Models 5310, 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 o
l
-penetration test.according to 49 CFR 173.465 (e) and free drop test according to 49 CFR 173.465 (c) (1).
The welds were examined and no visible damage was found.
l Model 5310 has been in use by both general and specific licensees since 1977 with no reported incidents of failure, i
EXTERNAL RADIATION LEVELS:
^
The manufacturer reports the maximum external radiation levels, 1
outside the direct beam path, for Models 5310, 5310-1, 5310-3 and l
5310-5 when loaded with maximum activity are the following:
I L
I
?
I REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: gy j g }gg PAGE 6 OF 10 j
i DEVICE TYPE:
Gamma Gauge EXTERNAL RADIATION LEVELS (Cont'd):
Measured radiation Distance levels (mrem /hr)
Models Model 5310, 5310-1 and 5310-3 5310-5 5 cm (1.97")
0.6
.1.5 30 cm (11.81")
<0.1 0.3 g
100 cm (39.37")
Background
Background j
1 QUALITY ASSURANCE AND CONTROL:
Loral Control Systems has supplied a quality assurance and i
control program which has been deemed acceptable for licensing j
purposes by the NRC. A copy of this program is on file with the j
NRC.
The assurance and control program consist of the.following
j In-process Inspection Assembly Inspection Receiving Inspection Structural Welding Processing Rejected Material LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:
Devices intended for distribution to persons spccifically licensed by the NRC or an Agreement State shall be labeled in accordance with Section 20.1901 of 10 CFR Part 20.
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.
m
~
1 REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: OCT 19 BH PAGE 7 OF 10 DEVICE TYPE:
Gamma Gauge LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE (Cont'd):
Devices intended for use under a general license shall be installed and initially tested for proper operation i
of the source exposure mechanism, safety warning 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.
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 CFR 31.5.
The device shall be leak tested at 6 month intervals using techniques capable of detecting 0.005 microcurie j
(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
t L
Since the effective date of this document, the Models 5310, 5310-1, 5310-3 and 5310-5 are not current products manufactured l
by the Lockheed Martin.
The total number of products still in L
use are 425.
The distributor had ceased all activities related to the manufacturing, sale, and distribution of this device and indicated that servicing to existing products would be performed l
by Honeywell-Measurex DMC Corporation.
r
l 1
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY) j NO.:
NR-582-D-803-B DATE: N319 Itu PAGE 8 OF 10 i
DEVICE TYPE:
Gamma Gauge I
SAFETY ANALYSIS
SUMMARY
(Cont'd):
The-devices were use'd to determine the thickness of copper, 1
steel, aluminum, or alloys.
The radioactive source is contained within a C.R.S.
cylinder located inside a steel housing.
A l
pneumatic operated-piston attached to the shutter controls the 1
l
. radiation beam.
When the shutter is in the "open" position, the primary beam exits the housing, is reduced in intensit y by the material undergoing measurement, and strikes the detector measuring system.
The output of the' measuring system is used for material j
i evaluation / control.
l l
i The gamma sources used in Models 5310, 5310-1, 5310-3, and 5310-5 j
have received ANSI N542-1977 classifications of 77C64444, 77C64444, 77E64444, and 77E64444 respectively.
The devices have j
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.
l This indicates that normal and accident conditions of use are highly unlikely to cause breach of containment integrity.
During i
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.
The distributor has submitted sufficient information to provide reasonable assurance that:
l The device can be safely operated by persons not having L
training in radiological protection.
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.
I REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE:
3119 WM PAGE 9 OF 10 DEVICE TYPE:
Gamma Gauge i
SAFETY ANALYSIS
SUMMARY
(Cont'd):
l Under accident conditions (such as fire and explosion) associated with handling, storage, and use of the
. device, it is unlikely that any person would' receive an l
external radiation dose or dose commitment in excess of the dose to the appropriate organ as specified in the following chart:
PART OF BODY rem /mSv Whole body; head and trunk; active blood-forming organs; i
gonads; or lens of eye 15/150 Hands and forearms; feet and ankles; localized areas of skin averaged over areas no larger than 1 cm2 (0.16 in2) 200/2000 Other organs 50/500 Operation of the shutter is con; rolled by a key lock.
This same l
locking system discourages unauthorized access to the source.
The device will be used in industrial environments; however, these environments 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 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.
Based on tP2 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 i
specific and general licensees.
Further, we conclude that the source housings can be expected to maintain their containment i
integrity adequately for normal conditions of use and for accidental conditions that might occur during use.
i I
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES j.
SAFETY EVALUATION OF DEVICE i
(AMENDED IN ITS ENTIRTY)
NO.:
NR-582-D-803-B DATE: OCT 19 Im PAGE 10 OF~10 DEVICE TYPE:
Gamma Gauge l
REFERENCES:
l
'The distributor has submitted the following supporting documents which are hereby incorporated by reference and are made a part of L-this registration document:
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, 1976, June 7, 1976, March 11, 1976, July 18, 1988, j
July 14, 1988, July 12, 1988, May 15,.1991, i
November 14, 1991 and January 10, 1992, with enclosures thereto.
Lockheed Martin's letter dated September 23, 1997.
Tremont Tech-Writers' letters dated March 27, 1998.
i ISSUING AGENCY:
U.S. Nuclear Regulatory Commission l
Date:
SCIIIISII Reviewer:
l J M W.
Lubinski rj GCT 191991 1
C Date:
Concurrence: /V -b
'Mo
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Baggett j
p i
l l
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l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.-
NR-582-D-803-B DATE:
00119IIII ATTACHMENT 1 a
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE (AMENDED IN ITS ENTIRTY)
NO.- NR-582-D-803-B DATE:
OCl II ATTACHMENT 2
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