ML20205S713
| ML20205S713 | |
| Person / Time | |
|---|---|
| Issue date: | 05/14/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20205S711 | List: |
| References | |
| FOIA-86-389 NUDOCS 8606120790 | |
| Download: ML20205S713 (53) | |
Text
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REGISTRY OF SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE N0: NR-169-S-161-S DATE: PAGE: 1 of 6 g$( ).4 M '
SOURCE TYPE: Gamma / Photon Source MODEL: C-235/C-236
/
MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
413 March Road P.O. Box 13500 Kanata, Ontario Canada K2K IX8 IS0 TOPE: MAXIMUM ACTIVITY:
Iodine-125 3 curies LEAK TEST FREQUENCY: 6 months PRINCIPAL USE: (T) Other CUSTOM DEVICE: YES X N0 e606120790 860609 PDR FOIA ROSE 86-389 PDR
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE N0: NR-169-S-161-S DATE: PAGE: 2 of 6
. gg 4 SOURCE TYPE: Gamma / Photon Source DESCRIPTION:
The Model C-235 inner capsule may be placed in a Model C-236 cylindrical brass holder 1.343 inches long and .625 inch 0.D. The walls of the holder are approximately .25 inches thick. The sealed source is held in the C-236 holder by a threaded brass bushing 0.2 inch diameter by 0.187 inch long. An optional 0.002 inch thick tin filter may be placed between the active end of the C-235 and the bushing. The holder is equipped with a brass end cap which provides approximately 1.4 inch of brass shielding.
Model C-235 Inner Capsule Iodine-125 absorbed into a 0.08 inch diameter spherical bead is
, encapsulated in a 1 inch long 316L stainless steel and aluminum capsule with a 0.124 inch 0.0. and a 20 mil wall. A spacer is used to position the charcoal or zealite bead at one end of the source rod and a stainless steel plug is welded in place to seal the capsule.
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REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE NO: NR-169-S-161-S DATE: PAGE: 3 Of 6 MAY 14 5 SOURCE TYPE: Gamma / Photon Source LABELING:
The source capsule is engraved with "AECL, I-125" and "C-235," and the source serial number. The outer source holder is engraved with "AECL, I-125" "C-236" and the holder serial number.
DIAGRAM:
See attached drawings of inner capsule assembly and outer source holder.
CONDITIONS OF NORMAL USE:
These sources would normally be incorporated in laboratory testing equipment such as bone mineral analyzers, etc. The use would normally be in clinical laboratory, industrial or other research laboratory environments under standard conditions of temperature and pressure.
PROTOTYPE TESTING:
By certificate dated May 24, 1972, the manufacture claims a classification of C-34334 for the Model C-235 inner capsule in accordance with standards established by Committee N542.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE N0: NR-169-S-161-S DATE: ggy 14 gggg PAGE: 4 of 6 SOURCE TYPE: Gamma / Photon Source EXTERNAL RADIATION LEVELS:
The following are radiation levels for the C-235/C-236 model. The inner capsule loading was 3 curies of Iodine-125.
(a) 0 contact with C236, shipping cap on with a 3 Ci .
content (Iodine-125) =100 mRh (b) 0 5.0 cm from the top surface of the capsule (C236), with the shipping cap on
=2.6 mRh (c) 0 30cm through the unobstructed window of C236 holder,
=2.9 Rh (d) 0 30cm, in beam, with shipping cap on
=.07 mRh (e) 0 100cm with shipping cap on
=.006 mRh QUALITY ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source. Weld quality is checked by destructive means on a test weld. After welding each source is checked for leakage by a hot liquid bubble test, and for contamination by a smear test. Activity limits for the intial smears are 0.0005 microcurie. The smear test is repeated after seven days and within seven days of shipment with an activity limit of 0.005 microcurie and also including any holder.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE NO: NR-169-S-161-S DATE: gpg 14 jgg6 PAGE: 5 of 6 SOURCE TYPE: Gamma / Photon Source SAFETY ANALYSIS
SUMMARY
Based on our review of the information and test data contained in the references cited below, we conclude that the Model C-235/C-236 source design is acceptable for licensing purposes. The basic source design was orginally approved for licensing purposes by the U. S. Atomic Energy Commission in 1969 for the use of a maximum of 500 millicuries of iodine-125, and more recently registered under registry number NR-169-S-156-S. The increased maximum activity of 3 curies of iodine-125 is not expected to hava a deleterious effect on source containment. Therefore, we conclude that the Model C-235/C-236 sealed source would be expected to maintain its containment integrity for normal conditions of use and accident conditions which might occur during uses specified in this certificate.
LIMITATIONS AND/0R CONSIDERATION OF USE:
The source shall be distributed only to persons specifically licensed by the NRC or Agreement States.
The source shall be leak tested at six month intervals using techniques capable of detecting 0.005 microcurie of removable contamination.
Handling, storage, use, transfer, and disposals: To be determined by the licensing authority.
The source shall not be subjected to environmental or other conditions of use which exceed the performance standard classification C34334 contained in ANSI N542, 1968.
This registration sheet and the information contained within the references shall not be changed without the written consent of the NRC.
o . .
e REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE N0: NR-169-S-161-S DATE: MAY 14 1955 PAGE: 6 of 6 SOURCE TYPE: Gamma / Photon Source
REFERENCES:
The following supporting documents for the model C-235/C236 sources are hereby incorporated by reference and are made a part of this registry document:
Atomic Energy of Canada, Limited letters dated January 24, 1984, and February 2, 1984 with enclosures thereto.
Atomic Energy of Canada, Limited letter dated January 8,1986 with enclosures thereto.
Atomic Energy of Canada, Limited letter dated April 25, 1986 with enclosures thereto.
ISSUING AGENCY:
U. S. NUCLEAR REGULATORY COMMISSION DATE N IIII REVIEWER _ . -
DATE WAY 14 Tif CONCURRENCE F
. .o REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR1695158U DATE: November 20, 1979 PAGE 10F 2 SEALED SOURCE TYPE: Sealed Source MODEL: C-265 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
Commercial Products P. O. Box 93
, Ottawa, Canada MANUFACTURER / DISTRIBUTOR:
ISOTOPE: Iodine-125 MAXIMUM ACTIVITY: 500 millicuries Gadolinium-153 100 millicuries '
LEAK TEST FREQUENCY:
PRINCIPAL USE: Industrial Radiography CUSTOM SOURCE: YES X NO Y
i REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR169S158U DATE: November 20, 1979 PAGE 2 0F 2 SEALED SOURCE TYPE: Sealed Source DESCRIPTION:
The Model C-265 source contains a maximum of 500 millicuries of iodine-125 in the form of Na! absorbed on charcoal or zeolite beads or a maximum of 100 millicuries of gadolinium-153 as GdCl absorbed on resin beads. The source consists of an annular aluminum body and body cover and is sealed with stycast 2762 epoxide sealant. The annular body measures 1.50 inches in diameter by 0.25 inches high and contains an annular grove 0.015 inches deep into which the radioactive material is placed. Minimum thickness is 0.020 inches.
LABELING:
Sources are engraved with; AECL, I-125 or Gd-153, C-265 and a serial number.
PROTOTYPE TESTING:
Tests conducted by the manufacturer indicate the source may be classified as C33334
? under the specifications established by ANSI.
REFERENCES:
Date November 20, 1979 Reviewed By /s/
Earl G. Wright Date November 20, 1979 Concurrence /s/
Joseph M. Brown, Jr.
ISSUING AGENCY:
U.S. Nuclear Regulatory Commission
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- j 'o* UNITED STATES .
8' ' 'n NUCLEAR REGULATORY COMMISSION
(, $ WASHINGTON, D. C. 20665
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AMENDMENT NO. 1 CERTIFICATE OF REGISTRATION AND SAFETY ANALYSIS
SUMMARY
SEALED SOURCE Manufacurer and Distributor Sealed Source Model Designation Atomic Energy of Canada Ltd C'-324 Ottawa, Canada
,y K2A 3W3 Isotope Maximum Activity I-125 Up to 500 Millicuries In accordance with request dated May 15, 1979, Catalogue Sheet dated Feburary 15, 1971 is amended as follows:
Change the sealed source description to read:
Description of Source Iodine-125 is absorbed into irregularly shaped charcoal chips or zeolite beads y and is encapsulated in a 316L stainless steel and aluminum capsule. The capsule is 0.384 inches long, 0.155 inches of which is aluminum. The overall diameter is 0.114 inches. A stainless steel plug is welded in place to seal the capsule. Minimum wall thickness of the source is 15 nils.
November 20, 1979 Date Reviewed 8 Y. / 5-Date 'lovember 20, 1979 Concurre By .-
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- j ,o, UNITED STATES ,
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NUCLEAR REGULATORY COMMISSION WASHING 7'.)N. D. C. 20555
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AMENDMENT NO. 1 CERTIFICATE OF REGISTRATION AND SAFETY ANALYSIS
SUMMARY
SEALED SOURCE Manufacturer and Distributor Sealed Source Model Designation Atomic Energy of Canada Ltd C-225/C-236, C-235/C-236 Ottawa, Canada K2A 3W3 Isotope Maximu Activity Iodine-125 Up to 500 millicuries In accordance with request dated May 15, 1979, Catalogue Sheet dated August 11, 1969 is amended as follows:
Change the sealed source description to read as follows:
Description of Source Either a C-225 or C-235 inner capsule may be placed in a C-236 cylindrical 4 brass holder 1.343 inches long and 5-inch 0.D. The walls of this holder are approximately 0.025 inch thick. The inner capsules are held in the C-236 holder by brazing a 2-mil thick tin filter over the source holder opening and pressing a 0.2-inch diameter by 0.187 inch long brass bush into place. The holder is equipped with a brass end cap which provides approximately 1/4 inch of brass shielding.
Model C-225 inner capsule: Iodine-125 electroplated on the end of a silver M re is encapsulated in a 1 inch long 316L stainless steel cylindrical capsule with a 0.124-inch 0.D. and 30-mil walls. The wire is held in place by means of a glass spacer and a stainless steel plug is welded in place to seal the capsule. The active portion of the source is positioned l at the end of the capsule.
Model C-235 inner capsule:
Iodine-125 absorbed into a 0.08-inch diameter spherical bead is encapsulated in a 1-inch long 316L stainless steel cylindrical capsule with a 0.124-inch 0.0. and a 20-mil wall. A spacer is used to position the charcoal or zeolite bead at one end of the source l
rod and a stainless steel plug 'is welded in place to seal the capsule.
i a e__ November 20, 1979 Reviewed By // '
Date N vember 20, 1979 Concurred By_..
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', 4 UNITED STATES 8i ' ,o NUCLEAR REGULATORY COMMISSION
$.- .. j WASHING TON, D. C. 20555
'+, ,e AMENDI1ENT FO. 1 CERTIFICATE OF REGISTRATION AND SAFETY ANALYSIS
SUMMARY
SEALED SOURCE Manufacturer and Distributor Scaled Source florfel Designation Atomic Energy of Canada Ltd. C-265 Ottawa, Canada K2A 3W3 ;
Isotope Maximum Activ1ty Iodine-125 500 millicuries Gadolinium-153 100 millicuries In accordance with request dated May 15, 1979 Catalogue Sheet dated August 11, 1969 is amended as follows:
Change the sealed source description to read:
Description of Source The Model C-265 source contains a maximum of 500 millicuries of iodine-125 e
in the form of NaI absorbed on charcoal or zeolite beads or a maximum of 100 millicuries of gadolinium-153 as GdCl absorbed on resin heads. The source consists of an annular aluminum body and body cover and is scaled ,
with stycast 2762 epoxide sealant. The annular body measures 1.50 inches in diameter by 0.25 inches high and contains an annular grove 0.015 inches deep into which the radioactive material is placed. 14fnfsum thickness is 0.020 inches. I Date Reviewed By_ dI
- d'Yb 'I
- f Date Concurred By .-
._m
, .: o REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (AMENDED IN ENTIRETY)
NO: NR-169-S-157-S DATE: PAGE: 1 of 5 ggg i 4 ggg 9
SOURCE TYPE: Gamma / Photon Source i
MODEL: C-324/C-236 i
MANUFACTURER / DISTRIBUTOR:
' ~
Atomic Energy of Canada, Ltd.
413 March Road P.O. Box 13500 Kanata, Ontario, Canada K2K 1X8 ISOTOPEi MAXIMUM ACTIVITY:
lodjne-125 3 curies .
4 LEAK TEST FREQUENCY: 6 months b
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P,RINCIPAL USE: (V) General Medical Use ,
CUSTOM DEVICE: YES X__NO
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REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (AMENDED IN ENTIRETY)
(CORRECTED COPY)
May 27, 1986 N0: NR-169-S-157-S DATE: h@d * *#E P[.GE : 2 Of 5 SOURCE TYPE: Gamma / Photon Source DESCRIPTION:
The model C-324 sealed source is for use as a Gamma /Photen source for general medical use such as for bone mineral analysis. The iodioe-125 which is absorbed into shaped charcoal beads or zeolite beads, is encapsulated in a 316 L stainless steel and aluminum capsule. The capsule is 0.384 inch long, 0.155 inch of which is aluminwn. The overall diamet r 's 0.114 inch.
A stainless steel plug is welded in place to seal the capsule. Minimum wall thickness of the source 0.015 inch. The C-324 sealed source is identical in design and construction (overall dimensions excepted-the C-324 is smaller in physical size) to the AECL sealed source model C-235. The Model C-324 sealed source may be placed in a Model C-236 cylindrical brass holder 1.343 inches long and 0.625 inches outside diameter. The walls of the holder are
, approximately 0.25 inches thick. The sealed source is held in the C-236 holder between a brass spacer at the welded end and a threaded brass bushing 0.2 inches diameter by 0.187 inches long. An optional 0.002 inches thick tin filter may be placed between the active end of the C-324 and the bushing. The holder is equipped with a brass and cap which provides approximately 1/4 inch of brass shielding.
LABELING:
The capsule is engraved on its stainless . steel cylindrical surface with "AECL",
"I-125", C-324 and serial number in chiracters 0.045 inch high X 0.005 inch maximum depth.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (AMENDED IN ENTIRETY)
NO: NR-169-S-157-S MAY 14 DATE: EM6 PAGE: 3 of 5 SOURCETr{f:, Gamma / Photon Source -
DIAGRAM:
See attached drawing.
CONDITIONS OF NORMAL USE:
This model source is for bone mineral analysis. The use would typically be in a clinical laboratory environment under standard conditions of temperature, g
PROTOTYPE TESTING:
The source is certified by the manufacturer to meet the ANSI standards under a classification of 68C 34334.
EXTERNAL RADIATION LEVFLS:
Refer to AECL Model C-235.
QL'All1Y ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source. Weld quality is checked by destructive means on a test weld. After welding each sourco is checked for leakage by a hot liquid bobble test and for contamination by a snwar test. Activity limits for the initial smears are 0.0005 microcurie. The smear test on the source is repeated after seven days and Within (Sven days of shipment with an activity }imit of 0.005 microcurie and also on any holder.
r REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE 1 (AMENDED IN ENTIRETY) I i
NO: NR-169-S-157-S DATE: E I4 1996 PAGE: 4 of 5 SOURCE TYPE: Gamma / Photon Source LIMITATIONS AND/0R CONSIDERATION OF USE:
The source shall be distributed only to persons specifically licensed by the NRC or Agreement States.
The source shall be leak tested at six month intervals using techniques capable of detecting 0.005 microcurie of removable contamination.
Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
The source shall not be subjected to environmental or other i conditions of use which exceed the performance standard classification C34334 contained in ANSI N542, 1968.
This registration sheet and the information contained within the references shall not be changed without the written consent of the NRC.
SAFETY ANALYSIS
SUMMARY
Based on our review of the information contained in the reference cited below, we conclude that the model C-324 source design continues to be acceptable for licensing purposes. The basic source design has been approved for the use of 500 mci of iodine-125 since 1977. The increased maximum activity of 3 curies of iodine-125 is not expected to have a deleterious effect on source containment. Therefore, we conclude that the model C-324 sealed sources would be expected to maintain their containment integrity for normal conditions of use and accident conditions which might occur during uses specified in this certificate.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (AMENDED IN ENTIRETY)
(CORRECTEDCOPY)
May 27, 1986 N0: NR-169-S-157-S DATE: IUOf14 E66 PAGE: 5 of 5 SOURCE TYPE: Gamma / Photon Source
REFERENCES:
The following supporting dccuments for the model C-324 sources are hereby incorporated by reference and are made a part of this registry document:
Atomic Energy of Canada, Limited letters dated February 2, 1984 with enclosures thereto.
Superseded Registration Certificate No. NR-169-S-157-S dated June 12, 1984 Atomic Energy of Canada, Limited letter dated January 8,1986 with enclosures thereto.
Atomic Energy of Canada, Limited letter dated April 25, 1986 with enclosures thereto.
ISSUING AGENCY:
U. S. NUCLEAR REGULATORY COMMISSION MAYt4 1996 DATE REVIEWER -
DATE UUU CONCURRENCE
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-5-157-5 DATE: JUh 1.,f384 PAGE 1 0F 6 SOURCE TYPE: Gamma / Photon Source MODEL: C-324 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
413 March Road P.O. Box 13500 Kanata, Ontario Canada K2K 1X8 ISOTOPE: MAXIMUM ACTIVITY:
Iodine-125 3 Curies Cadmium-109 0.2 Curies Gadolinium-153 1 Curie Ytterbium-169 5 Curies Thulium-170 5 Curies Tellurium-125m 0.5 Curies LEAK TEST FREQUENCY: 6 months l
l PRINCIPAL USE: (V) General Medical Use
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i CUSTOM DEVICE: YES X NO l
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f
' REGISTRY OF RADI_0 ACTIVE SEALED SOURCES.AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
.e NO.: NR-169-S-157-5
'DATE: JUk i 2 G84 PAGE 2 0F 6 SOURCE TYPE: Gamma / Photon Source DESCRIPTION:
The model 324 sealed source is for u_se as a Gamma / Photon source for general medical use sucii as for bone mineral analysis. The radionuclide, for example, iodine-125 which is absorbed into irregularly shaped charcoal chips or zeolite beads, is encapsulated ~in a 316 L stainless steel and aluminum capsule. The capsule'is 0.384 inch l'ong, 0.155 inch of which is aluminum. The overall diameter is 0.114 inch. - A stainless steel plug is welded in place to seal the capsule. Minimum wall thickness of the source 0.015 inch. The C-234 sealed source is identical in design and construction (overall divisions excepted-the C-324 is smaller in physical size) to the AECL sealed source model C-235.
Additional radionuclides instead of iodine may be incorporated as follows:
o Cadmium-109 is absorbed on ion exchange' medium or electro deposited as metallic cadmium on a suitable substrate such as silver, gold, platin~m u or nickel. -
o Cadolinium-153 is absorbed on ion exchange medium or as a pressed pellet of gadolinlum~ oxide.
o Ytterbium-169 is absorbed on ion exchange medium or as pressed pellet of ytterbium oxide or as a pellet of metallic ytterbium, o Thulium-170 is absorbed on ion exAhange medium or as a pellet of metallic thulium.
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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICE 3 SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-S-157-5 DATE: , jig; 7 p 7gg4 PAGE 3 0F 6 SOURCE TYPE: Gamma / Photon Source DESCRIPTION (cont.):
o Te11urlum-125m is absorbed on ion exchange medium or as pressed pellet of tellurium oxide.
LABELING:
The capsule is engraved on its stainless steel cylindrical surface with "AECL",
"I-125" (or other radionuclide), and serial number as specified in characters 0.045 inch high X 0.005 inch maximum depth.
i DIAGRAM:
See attached drawing.
CONDITIONS OF NORMAL USE:
This model source is for bone mineral analysis. The use would typically be in I
a clinical laboratory environment under standard conditions of temperature.
PROTOTYPE TESTING:
I The source is certified by the manufacturer to meet the ANSI standards under a classification of 68C 34334.
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REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
N0.: NR-169-5-157-5 DATE: PAGE 4 0F 6 J@i ;p ggy SOURCE TYPE: Gamma / Photon Sourc9 EXTERNAL RADIATION LEVELS:
Refer to AECL Model C-235.
QUALITY ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source. Weld quality is checked by destructive means. Each source is checked for leakage by a hot liquid bubble test within seven days of final packaging, and each source is checked for contamination by smearing the source. Activity limits for the smears are 0.0005 microcurie. The smear test is repeated after i
seven days or more with an activity limit of 0.005 microcurie.
l l LIMITATIONS AND/0R CONSIDERATION OF USE:
(
o The source shall be distributed only to persons specifically licensed by the NRC or Agreement States.
o The source shall be leak tested at six month intervals.using techniques capable of detecting 0.005 microcurie of removable contamination.
o Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
o The source shall not be subjected to environmental or other conditions of use which exceed the performance standard classification C34334 l
contained in ANSI N5.4, 1968.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-S-157-S DATE: PAGE 5 0F 6 0Uk. 1 ? 1984 SOURCE TYPE: Gamma / Photon Source LIMITATIONS AND/0R CONSIDERATION OF USE:
o This registration sheet and the information contained within the references shall not be changed or transferred without the written consent of the NRC.
SAFETY ANALYSIS
SUMMARY
Based on our review of the information contained in the reference cited below, we conclude that the model C-324 source design continues to be acceptable for licensing purposes. The basic source design has been approved for the use of 500 mci of iodine-125 since 1977. The increased maximum activity of 3 curies of iodine-125 and the use of the additional radionuclides and their respective maximum activities listed in this certificate are not expected to have a deleterious effect on source containment. Therefore, we conclude that the model C-324 sealed sources would be expected to maintain their containment integrity for normal conditions of use and accident conditions which might occur during uses specified in this certificate.
REFERENCES:
The following supporting documents for the model C-324 sources are hereby incorporated by reference and are made a part of this registry document:
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
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l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-S-157-S DATE: JIlN 1 2 igg 4 PAGE 6 0F 6 SOURCE TYPE: Gamma / Photon Source ,,
REFERENCES:
o Atomic Energy of Canada, Limited letters dated February 2, 1984, and enclosures thereto.
o Superseded Registration Certificate No. NR-169-S-157-5, dated November 20, 1979.
Date Reviewed Date Concurrence ISSUING AGENCY U.S. Nuclear Regulatory Commission l
. l
. 1 REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Corrected Copy)
NO.: NR-169-S-156-S DATE: PAGE 1 0F 4 rijpj 7 J. E64 SEALED SOURCE TYPE: Gamma / Photon Source MODEL: C-225/C-236 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
Commercial Products P.O. Box 13500 Kanata, Ontario Canada K2K 1X8 ISOTOPE: MAXIMUM ACTIVITY:
g Iodine-125 500 mil 11 curies LEAK TEST FREQUENCY: 6 months PRINCIPAL USE: (T) Other CUSTOM DEVICE: YES X NO 9
i
. T REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Corrected Copy)
NO.: HR-169-S-156-5 DATE: ' 'S ~8 E04 PAGE 2 0F 4 SEALED SOURCE TYPE: Gamma / Photon Source DESCRIPTION:
The C-225 inner capsule may be placed in a C-236 cylindrical brass holder 1.343 inches long and 5/8 inch 0.D. The walls of this holder are approximately 0.025 inch thick. The inner capsule is held in the C-236 holder by brazing a 2-mil thick tin filter over the source holder opening and pressing a 0.2-inch diameter by 0.187 inch long brass bush into place. The holder is equipped with a brass end cap which provides approximately 1/4 inch of brass shielding.
Model C-225 inner capsule: Iodine-125 electroplated on the end of a 9 silver wire is encapsulated in a 1 inch long 316L stainless steel cylindrical capsule with a 0.124-inch 0.D. and 30-mil walls. The wire is held in place by means of a glass spacer and stainless steel plug is welded in place to seal the capsule. The active portion of the source is positioned at the end of the capsule.
LABELING:
The inner capsules are engraved with "AECL, I-125, C-225" and the source serial number. The outer source holder is engraved with "AECL, I-125, C-236,"
and the source serial number.
r REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Corrected Copy)
NO.: NR-169-S-156-S DATE: jyp; 1; ggg4 PAGE 3 0F 4 SEALED SOURCE TYPE: Gamma / Photon Source QUALITY ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source. Weld quality is checked by destructive means. Each source is checked for leakage by a hot liquid bubble test within seven days of shipment, and each source is checked for contamination (both inner and outer capsules) by dry smearing the source. Activity limits for the smears are 0.005 microcurie on the inner capsule and 0.0005 microcurie on the outer capsule. The smear test is repeated after seven days or more and within seven days of shipment.
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REFERENCES:
Date: November 20, 1979 Reviewed: Earl G. Wright Date: November 20, 1979 Concurrence: Joseph M. Brown Jr.
ISSUING AGENCY:
" 5. Nuclear Regulatory Commission i
1
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Corrected Copy)
NO.: NR-169-S-156-S DATE: DON I E 1984 PAGE 4 0F 4 SEALED SOURCE TYPE: Gamma / Photon Source -
NOTE:
This corrected copy deletes the Model C-235/C-236 source from this Registration Certificate effective upon the issuance of Certificate No.
NR-169-5-161-5.
Date ,
Reviewed ..
p Date Concurrence
~
. i REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE DATE: November 20, 1979 PAGE 10F 3 N0.: NR169S156$$
SEALED SOURCE TYPE: Gamma Source MODEL: C-225/C-236, C-235/C-236 MANUFACTURER / DISTRIBUTOR: Atomic' Energy of Canada, Ltd.
Commercial Products P. O. Box 93 Ottawa, Canada MANUFACTURER / DISTRIBUTOR:
ISOTOPE: Iodine-125 MAXIMUM ACTIVITY: 500 millicuries.
LEAK TEST FREQUENCY:
PRINCIPAL USE: Other CUSTOM SOURCE: YES X NO l .
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REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES -
SAFETY EVALUATION OF SEALED SOURCE N0.: NR169S156U DATE: November 20, 1979 PAGE 2 0F 3 SEALED SOURCE TYPE: Gamma Source DESCRIPTION:
Either a C-225 or C-235 inner capsule may be placed in a C-236 cylindrical brass
' holder 1.343 inches long and 5-inch 0.D. The walls of this holder are approximately 0.025 inch thick? The inner capsules are held in the C-236 holder by brazing a 2-mil thick tin filter over the source holder opening and pressing a l 0.2-inch diameter by 0.187 inch long brass bush into place. The holder is equipped i with a brass end cap which provides approximately 1/4 inch of brass shielding.
l Model C-225 inner capsule: Iodine-125 electroplated on the end of a silver wire is encapsulated in a 1 inch long 316L stainle'ss steel cylindrical capsule with a 0.124-inch 0.D. and 30-mil walls. The wire is held in place by means of a glass spacer and a stainless steel plug is, welded in place to seal the capsule. The active portion of the source is positioned at the end of the
! capsule.
Model C-235 inner capsule: Iodine-125 absorbed into a 0.08-inch diameter spherical bead is encapsulated in a 1-inch long 316L stainless steel l cylindrical capsule with a 0.124-inch 0.D. and a 20-mil wall. A spacer is
- used to position the charcoal or zeolite bead at one end of the source rod and l a stainless steel plug is welded in place to seal the capsule.
l LABELING:
The inner capsules are engraved with "AECL, I-125, C-225" or "C-235", and the
! source serial number. The outer source holder is engraved with "AECL, I-125, l C-236," and the source serial number.
OUALITY ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source.
Weld quality is checked by destructive means. Each source is checked for leakage by a hot liquid bubble test within seven days of shipment, and each source is checked for contamination (both inner and outer capsules) by dry smearing the source. Activity limits for the smears are 0.005 microcurie on the inner capsule l and 0.0005 microcurie on the outer capsule. The smear test is repeated after seven i days or more and within seven days of shipment.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR169S156U DATE: November 20, 1979 PAGE 3 0F 3 SEALED SOURCE TYPE: Gamma Source
REFERENCES:
Date November 20, 1979 Reviewed By /s/
Earl G. Wright Date November 20, 1979 Concurrence /s/
Joseph M. Brown, Jr.
ISSUING AGENCY:
U. S. Nuclear Regulatory Comission .
b' ' ' ' s' mu . _ _ . . _ _.. __
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR169S151U DATE: October 1977 PAGE 10F 2 SEALED SOURCE TYPE: Gamma Irradiator Source MODEL: C-198 MANUFACTURER /DISTRIBJ' TOR: Atomic Energy of Canada, Ltd.
Commercial Products P. O. Box 93 Ottawa, Canada MANUFACTURER /0ISTRIBUTOR:
ISOTOPE: Cobalt-60 MAXIMUM ACTIVITY: 3,500 curies f
LEAK TEST FREQUENCY:
PRINCIPAL USE: Gamma Irradiator, Category I
- CUSTOM SOURCE
- YES X NO l
l
s.
~ '
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR1695151U DATE: October 1977 PAGE 2 0F 2 SEALED SOURCE TYPE: Gamma Irradiator Source DESCRIPTION:
The Mode 1 C-198 is a doubly encapsulated fusion welded source.
The Model C-198 outer capsule, constructed of 316L stainless steel, has a length of 8.265 inches, a diameter of 0.441 inch and a wall thickness of 0.025 inch. The 0.025 inch thick end caps of the Model C-198 outer capsule are sealed by fusien welds.
The inner capsule assembly, constructed of 316L stainless steel, is sealed by fusion welded 0.025 inch thick end caps. The length of the inner capsule assembly is 8.015 inches and the diameter if 0.337 inch. The wall thickness is 0.025 inch.
The active volume contains up to seven 1-inch long by 0.250 inch diameter cobalt
' slugs or 1 mm by 1 mm cylindrical pellets. The slugs may be nickel plated or unplated.
The maximum activity for each Model C-198 source is 3.5 kCi Co-60 for either slug material or pellet material.
LABELING:
The C-198 capsule is engraved on its outer surface with "AECL," "Co-60," "C-198,"
and serial number. The inner capsule is also engraved on its outer surface with a serial number.
ISSUING AGENCY:
U.S. Nuclear Regulatory Commission l
l
e REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR169S1500 DATE: October 1977 PAGE 10F 2 SEALED SOURCE TYPE: Garra Irradiator Source MODEL: C-185 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
Commercial Products P. O. Box 93 Ottawa, Canada MANUFACTURER / DISTRIBUTOR:
ISOTOPE: Cobalt-60 MAXIMUM ACTIVITY: 1,250 curies N
s -
LEAK TEST FREQUENCY:
PRINCIPAL USE: Gamma Irradiator, Category I CUSTOM SOURCE: YES X NO I
f h
4
, . . +
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR16951500 DATE: October 1977 PAGE 2 0F 2 SEALED SOURCE TYPE: Gamma Irradiator Source DESCRIPTION:
The Model C-185 is a doubly encapsulated fusion welded source. The Model C-185 source contains up to seven sheathed inner capsules.
The Model C-185 outer capsule, constructed uf 316L stainless steel, has a length of 8.265 inches, a diameter of 0.441 inch and a wall thickness of 0.025 inch. The 0.031 inch thick end caps of the Model C-185 outer capsule are sealed by fusion l welds.
The inner capsule assembly, constructed of Type 25-H aluminum, is sealed by fusion welding. The length of the inner capsule assembly is_1.13 inches and the diameter is 0.375 inch. The wall thickness is 0.062 inch. The active volure contains a 1-inch long by 0.250 inch diameter cobalt slug.
The maximum activity for each Model C-185 source is 1.25 kCi Co-60.
LA8ELING:
i The Model 185 capsule is engraved on its outer stainless steel cylindrical surface with "AECL", "Co-60", "C-185", and serial number.
PROTOTYPE TESTING:
The manufacturer certifies that the Model C-185 will meet the standards of ANSI classification E44434 based on comparisons and calculations.
ISSUING AGENCY:
U.S. Nuclear Regulatory Commission
, _ _ _ ~ - _ _ , - _,____m.-_.,
1
\
i ... ;
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR1695149U DATE: July 1977 PAGE 10F 2 SEALED SOURCE TYPE: Teletherapy Source PODEL: XC-325 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada Ltd.
Commercial Products P. O. Box 93 Ottawa, Canada MANUFACTURER / DISTRIBUTOR:
ISOTOPE: Cobalt-60 MAXIMUM ACTIVITY: 12,000 curies LEAK TEST FREQUENCY:
PRINCIPAL USE: Medical Teletherapy CUSTOM SOURCE: YES X 4K) i 9
I 1
- ..y REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.
- NR169S149U DATE: July 1977 PAGE 2 0F 2 SEALED SOURCE TYPE: Teletherapy Source DESCRIPTION:
The Atomic Energy of Canada, Ltd. (AECL) sealed source Model XC-325 consists of doubly encapsulated cobalt-60 pellets for use as a gamma source. Active material is in the form of cylindrical nickel-plated cobalt metal pellets 0.039 inches (1.0 nillimeter) diameter by 0.039 inches (1.0 millimeter) long. The p'ellets are free loaded into the inner capsule which is sealed by fusion welding techniques. The singly encapsulated inner capsule (minimum wall thickness 0.022 inches) is loaded into an outer capsule (minimum wall thickness 0.022 inches) and is sealed by fusion welding techniques. Construction of the capsules is from Type 316L stainless steel. Overall outside length is 1.446 inches and the overall outside diameter is 0.922 inches. The source is designed for use with Philips Medical teletherapy units.
LABELING:
The inner encapsulation is engraved with the following:
! "AECL," " cobalt-60," serial number and XC-325.
The outer encapsulation is engraved with the following:
"AECL," cobalt-60, serial number and XC-325.
- PROTOTYPE TESTING:
The AECL Model XC-325 sealed source has been tested by the manufacturer and, together with an engineering analysis, a classification of C54524 has been assigned pursuant to ANSI classification system No. N43.3-1967.
OUALITY ASSURANCE AND CONTROL:
i Each capsule is wipe tested to an acceptance level of 0.005 microcuries before
, transfer to the customer.
l t ISSUING AGENCY:
l U.S. Nuclear Regulatory Commission l
l l
1
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-5 DATE: JAN 2 3 19o5 PAGE 1 0F 6 SOURCE TYPE: Gamma Irradiator Source MODEL: C-188 (Series) Type 1, 2, 3, 4, 5, and 6 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
413 March Road P.O. Box 135C0 Kanata, Ontario, Canada K2K1X8
- ISOTOPE: MAXIMUM ACTIVITY:
Cobalt-60 17,000 curies LEAK TEST FREQUENCY: 6 months PRINCIPAL USE: (J) Gamma Irradiator, Category I, II, III, IV CUSTOM SOURCE: YES X NO
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NA NR-169-S-142-S DATE: e PAGE 2 0F 6 7y SOURCE TYPE: Gamma Irradiator Source DESCRIPTION:
The Model C-188 is a doubly encapsulated fusion welded source. All Model C-188 sources have the same outer capsule. The inner capsules vary with the source type. The Model C-188, Type 1 source contains two Model C-177 inner capsules; Type 2 contains two Model AC-191 inner capsules; Type 3 contains two Model AC-195 inner capsules; and Type 4 contains one Model C-246 inner capsule.
The Model C-188 outer capsule, constructed of 316L stainless steel, has a length of 17.777 inches, a diameter of 0.437 inch and a wall thickness of 0.025 inch. The 0.025 inch thick end caps of the Model C-188 outer capsule are sealed by fusion welds.
The Model C-177 inner capsule assembly, constructed of non-radioactive 316 stainless steel, is sealed by fusion welded 0.025 inch end caps. The length of the Model C-177 inner capsule assembly is 8.25 inches and the diameter is 0.317 inch. The wall thickness is 0.025 inch. The active volume of the capsule has a length of 8.0 inches and a diameter of 0.267 inches. The active volume contains either eight 1 inch long by 0.250 inch diameter cobalt slugs of 1 mm by 1 mm cylindrical pellets.
The Model AC-191 inner capsule assembly is identical to the Model C-177 inner capsule assembly except that the Model AC-191 is irradiated as a complete capsule making the stainless steel radioactive.
The Model AC-195 inner capsule assembly is essentially the same as the Model C-177 and the AC-191 except the material of construction is Zircaloy-2.
The Model AC-195 is irradiated as a complete capsule making the Zircaloy-2 radioactive.
The Model C-246 inner capsule is constructed of 316L stainless steel and is sealed by fusion welded 0.025 inch end caps. The capsule is 16.485 inches long: times 0.32 inch outside diameter with a wall thickness of 0.025 inch.
The maximum activity for each Model C-188, 3 source is 17 kilocurie Cobalt-60 for slug material and 14 kilocurie Cobalt-60 for pellet material.
The AC-339 model is essentially identical, both in materials and construction,
.____._.____m__ _ . - . . _ . _ _ _ .
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-S DATE: PAGE 3 0F 6 jsf; 29 1985 SOURCE TYPE: Gamma Irradiator Source to the AC-195 model with exception of the " bull nose" machine at one end. The material of this capsule is Zircaloy-2 or 4. - The wall thickness and the design of the closure end welds are identical to those of the AC-195 model.
The AC-345 model is again similar to the AC-195 model with exception of the overall length. The AC-195 is 8.250 inches long whereas the AC-345 is 11.187 inches long. The structural material for the AC-345 is again Zircaloy-2 or 4. The wall thickness and the design of the closure end welds are identical for both models. The C-348 model is similar to the C-177 model except for the overall length of 5.312 inches. The structural material, wall thickness and the design of closure end welds are identical for both models.
The configurations of the C-188 assembly are summarized in the following table:
C-188 Type Model Number Number Of Number Of Inner Inners 1 C-177 2 2 AC-191 2 3 AC-195 2 -
4 C-246 1 5 AC-339 2 6 AC-345/C-348 1/1 LABELING:
Each model C-177, AC-191, AC-195, C-246, AC-339, AC-345, and C-348 inner
. capsule assembly is engraved on the end capsule with a serial number., The Model C-188 source is engraved on the upper end cap face with the last three l digits of the serial number underlined. The serial number and "C-188" are engraved on the diameter of the upper end cap. The diameter of the lower end cap is engraved "AECL" and "Co-60."
DIAGRAM:
See Attachment 1.
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO.NR-169-S-142-S DATE: pAGE 4 0F 6 JAN 2 9 19ES SOURCE TYPE: Gamma Irradiator Source CONDITIONS OF NORMAL USE:
The source Model C-188 is designed primarily for use in AECL irradiators which utilize Cobalt-60 as a radiation source.
PROTOTYPE TESTING:
C-188 source assembly, Types 1, 2, 3, 4, 5, and 6 was demonstrated to meet Requirements ANSI N5.10-1968 (superseded by ANS N542-1977) under the Classification No. E54434. Review of test parameters and configurations of Types 5 and 6 indicates that no change in the integrity of the C-188 assembly is expected. The main difference is between Types 1, 2, 3, 5, and Type 6. The position of the joint between the two inner capsules in the Type 6 is moved from the center of the assembly towards one end. In addition, an unirradiated AC-339 model passed the requirements of ANSI Classification E43424.
The additional tests which are specified in ANSI N43.10 " Safe Design and Use of Panoramic Wet Source Storage Gamma Irradiators" have also been reviewed. As a result the Bend Test was performed on Types 2, 3, 4, and 5. The tests are described in AECL test report "C-188 Bend Test," dated September 1984. Type 1 was not tested since, in terms of bend test parameters, it is the same as -
Type 2. Type 6 was not tested either since it is similar to Types 2 and 3.
The test report indicates that if the force is applied in the location where the two inner capsules join, a fracture of the outer capsule can occur. Further, the test report indicates that if the force is applied away from that location ,
the outer capsule remains intact. Leak tests, as defined in ANSI N542-1977, paragraph A2.2.1, Vacuum Leak Bubble Test, were performed in all test specimens.
In the case of the four assemblies where the outer capsule ruptured, tests were l performed on the inner capsules. In all cases the Cobalt-60 containment main-tained its integrity. .
l
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I e
. - , - , , - - - , . - - - , - -,--- -r-ev-- - .- - - . g-
i REGISTRY OF RADIDACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy) ,
NO. NR-169-S-142-S
~ DATE: PAGE 5 0F 6
,gg 29 1985
_ SOURCE TYPE: Gamma Irradiator Scurce EXTERNAL RADIATION LEVELS:
A calculation of do:n rates was done using the gamma radiation constant of Cobalt-60 of 1.32 R/nr at 1 meter / curie. A source containing 17,000 curies would yield the following dose rates:
R/hr cm 22,440 T00 249,990 30 8,976,000 5 QUALITY ASSURANCE AND CONTROL:
The quality control has previously been deemed acceptable for licensing purposes by the U.S. NRC.
LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE: -
7 The source shall be distributed only to persons specifically licensed by the NRC or an Agreement State. -
The source shall be leak tested at six (6) month intervals using techniques capable of detecting 0.005 microcurie of removable contamination.
Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
- This source shall not be subjected to environmental or other conditions of use which exceed ANSI Classification E54434.
AECL will amend this registration sheet each time they add a new type to the series.
This registration sheet and the information contained within the references shall not be changed or transferred without the written consent of the NRC.
REGISTRY OF RADI0 ACTIVE SEALED 30JRCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
-NO.
NR-169-S-142-5 OATE: PAGE 6 0F 6
,gh ? ? IMS SOURCE TYPE: Gamma Irradiator Source SAFETY ANALYSIS
SUMMARY
Based on our review of the information and test data cited below the claimed ANSI classification, we continue to conclude that the Model C-188 design is acceptable for licensing purposes. This amendment adds two additional inner capsul.es to F.he previously approved design. Furthermore, we conclude that these sources would he expected to maintain their containment integrity for normal conditions of use and accidental conditions which might occur during the uses specified in this certificate.
REFERENCES:
The following suppot ting documents for the Model C-188 are hereby incorporated by reference and are made a part of this registry document.
Atomic Energy of Canada, Ltd. letters with attachments dated October 29, 1973, and September 20, 1984.
Supersedes NRC Registry Document No. NR-169-S-142-0 dated November 21, 1973.
ISSUING AGENCY U.S. Nuclear Regulatory Commission JAN 2 9 1985 Date: .
Reviewer: ___
Dater , M t ? iv. * '
8 Concurrence: Uma r
4 d u (...
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SodRCE (AmendedCopy)
No. NR-169-S-142-5 DATE: tytt 2 3 yds $ PAGE 10F 6 SOURCE TYPE: Gamma Irradiator Source M00EL:
C-188(Series) Type 1to12, inclusive.
MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd, 413 March Poid P.O. Box 13500 Kannt&, Ontario, Canada K2K1XS
- ISOTOPE:
MAXIMUMACTIVfJY:
Cobalt-60 17,000 Curies (slug material) 14,000 Curies (pellet material)
LEAK TEST FREQUENCY: 6 months PRINCIPAL USE: (J) Gamma Irradiator, Category I, II, III, IV CUSTOM SOURCE: ,
_YES X NO
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
& NR-169-S-142-S DATE: PAGE 2 0F 6 3 u .e SOURCE TYPE: Ganna Irraniator founce DESCRIPTION:
The Model C-188 is a doubly encapsulated fusion welded source. All Model C-188 sources have the same outer capsule. The inner capsules vary with the source type according to the combinations shown on page 3. The inner capsule Mode'l Numbers are C-177, AC-191. AC-195, C-246, AC-339, AC-345, and C-348.
The Model C-183 outer capsule, constructed of 316L stainless steel, has a length of 17.777 inches, a diameter of 0.437 inch and a wall thickness of 0.025 inch. The 0.025 inch thick end caps of the Mcdel C-188 outer capsule are sealed by fusion welds.
The Model C-177 inner capsule assembly, constructed of non-radioactive 316 stainless steel, is sealed by fusion welded 0.025 inch end caps. Tne length of the Model C-177 inner capsule assembly is 8.25 inches and the diameter is 0.317 inch. The wall thickness is 0.025 inch. The active volu.ne of the capsule has a length of 8.0 inches and a diameter of 0.267 inches. The active volume contains either eight 1 inch long by 0.250 inch diameter ccbalt y slugs of 1 mm by 1 mm cylindrical pellets.
The Mcdel AC-191 inner capsule assembly is identical to the Model C-177 inner capsule assembly except that the Model AC-191 is irradiated as a complete capsule making the stainless steel radioactive.
The Model AC-195 inner capsule assembly is essentially the same as the Model C-177 and the AC-191 except the material of construction is Zircaloy-2.
The Model AC-195 is irradiated as a complete capsule making the Zircaloy-2 '
radioactive.
The Model C-246 inner capsule is constructed of 316L stainless steel and is sealed by fusion welded 0.025 inch end caps. The capsule is 16.485 inches long times 0.32 incn outside diameter with a wall thickness of 0.025 inch.
The maximum activity for each Model C-188 source is 17 kilocurie Cobalt-60 for slug haterial and 14 kilocurie Cobalt-60 for pellet material.
The AC-339 model is essentially identical, both in materials and construction, 1
h b
a
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-5 DATE:
DEC 2 3 E65 PAGE 3 0F 6 SOURCE TYPE: Gamma Irradiator Source to the AC-195 model with exception of the " bull nose" machined at one end. The material of this capsule is Zircaloy-2 or 4.
of the closure end welds are identical to those of the AC-195 model.The wall thickne The AC-345 overall length. model is again similar to the AC-195 model with exception of the The AC-195 is 8.250 inches long whereas the AC-345 is 11.187 or 4 inches long. The structural material for the AC-345 is again Zircaloy-2 The for both models. wall thickness and the design of the closure end welds are identical overall length of 5.312 The C-348 inches. model is similar to the C-177 model except for the The structural material, wall thickness and the design of closure end welds are identical for both models.
The configurations of the C-188 assembly are summarized in the following table:
C-188 Type Model Number C-188 Type Model Number Number Of Inners Number Of Inners 1
C-177/C-177 7 2 C-177/AC-191 AC-191/AC-191 8 3 C-177/AC-195 AC-195/AC-195 9 4 C-246 C-177/AC-339 10 AC-191/AC-195 5 AC-339/AC-339 11 AC-191/AC-339 6 AC-345/C-348 12 AC-195/AC-339
_ LABELING:
Each model C-177, AC-191, AC-195, C-246, AC-339, AC-345, and C-348 inner capsule assembly is engraved on the end capsule with a serial number. The Modril C-188 source is engraved on the upper end cap face with the last three digits of the serial number underlined.
The serial number and "C-188" are engraved on the diameter cap is engraved "AECL" and "Co-60 "of the upper end cap. The diameter of the lower end DIAGRAM:
See Attachment 1.
~
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-S DATE: PAGE 4 0F 6 SOURCE TYPE: Gamma Irradiator Source CONDITIONS OF NORMAL USE:
l The source Model C-188 is designed primarily for use in AECL frradiators which utilize Cobalt-60 as a radiation source.
PROTOTYPE TESTING:
C-188 source assembly, Types 1, 2, 3, 4, 5, and 6 was demonstrated to meet Requirements ANSI N5.10-1968 (superseded by ANSI N542-1977) under the Classification No. E54434. Review of test parameters and configurations of Types 5 and 6 indicates that no change in the integrity of the C-188 assembly
'is expected. The main difference is between Types 1, 2, 3, 5, and Type 6. The position of the joint between the two inner capsules in the Type 6 is moved from the center of the assembly towards one end. In addition, an unirradiated AC-339 model passed the requirements of ANSI Classification E43424.
The additional tests which are specified in ANSI N43.10 " Safe Design and Use of Panoramic Wet Source Storage Gamma Irradiators" have also been reviewed. As a result the Bend Test was performed on Types 2, 3, 4, and 5. The tests are described in AECL test report "C-188 Bend Test," dated September 1984. Type I was not tested since, in terms of bend test parameters, it is the same as Type 2. Type 6 was not tested either since it is similar to Types 2 and 3.
The test report indicates that if the force is applied in the location where the two inner capsules join, a fracture of the outer capsule can occur. Further, the test report indicates that if the force is applied away from that location the outer capsule remains intact. Leak tests, as defined in ANSI N542-1977, paragraph A2.2.1, Vacuum Leak Bubble Test, were performed on all test specimens.
In the case of the four assemblies where the outer capsule ruptured, tests were performed on the inner capsules. In all cases the Cobalt-60 containment main-tained its integrity.
t REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-S 3 O DATE: PAGE 5 0F 6 SOURCE TYPE: Gamma Irradiator Source EXTERNAL RADIATION LEVELS:
A calculation of dose rates was done using the gamma radiation constant of Cobalt-60 of 1.32 R/hr at I meter / curie. A source containing 17,000 curies would yield the following dose rates.
R/hr cm 22,440 T00 249,990 30 G,976,000 5 QUALITY ASSURANCE AND CONTROL; The quality control has previously been deemed acceptable for licensing purposes by the U.S. NRC.
LIMITATIONS AND/0R OTHER CONSIDERATIONS OF USE:
?
- The source shall be distributed only to persons specifically licensed by the NRC or an Agreement State. -
The source shall be leak tested at six (6) month intervals using techniques capable of detecting 0.005 microcurie of removable contamination.
Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
This source shall not be subjected to environmental or other conditions of use which exceed ANSI Classification E54434.
AECL will request and receive an amendment of this registration sheet prior to adding a new type to the C-188 Series.
This registration sheet and the information contained within the references shall not be changed or transferred without the written consent of the NRC.
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES .
SAFETY EVALUATION OF SOURCE (Amended Copy)
NO. NR-169-S-142-5 DATE: -. 2 $ (V$ PAGE 6 0F 6 SOURCE TYPE: Gamma Irradiator Source SAFETY ANALYSIS
SUMMARY
Based on our review of the information and test data cited below, including the claimed ANSI classification, we continue to conclude that the Model C-188 desicjn is acceptable for licensing purposes. This amendment adds six new combinations of the same inner capsules of the previously approved designs. Furthermore, we j conclude that these sources would be expected to maintain their containment integ-rity for normal conditions of use and accidental conditions which might occur during the uses specified in this certificate.
REFERENCES:
The following supporting documents for the Model C-188 are hereby incorporated by reference and are made a part of this registry document.
Atomic Energy of Canada, Ltd. letters with attachments dated October 29, 1973, September 20, 1984, and July 18, 1985.
Supersedes NRC Registry Document No. NR-169-S-142-S dated January 29, 1985.
ISSUING AGENCY U.S. Nuclear Regulatory Commission Date: 2"2.11%
Reviewer:
Date: b/,
Concurrence: M. g 6 - . w.
U' /
i
o .
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-5-135-S DATE: JGh 12 884 PAGE 1 0F 6 SOURCE TYPE: Gamma / Photon Source MODEL: C-281 MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
413 March Road P.O. Box 13500 Kanata, Ontario Canada K2K 1X8 ISOTOPE: MAXIMUM ACTIVITY:
Iodine-125 3 Curies l Cadmium-109 0.2 Curies Gadolinium-153 1 Curie
! Ytterbium-169 5 Curies l Thulium-170 5 Curies 1
Te11urium-125m 0.5 Curies LEAK TEST FREQUENCY: 6 months PRINCIPAL USE: (T) Other l
CUSTOM DEVICE: YES X No
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-S-135-S DATE: MI#M PAGE 2 0F 6 SOURCE TYPE: Gamma / Photon Source DESCRIPTION:
The AECL C-281 source and holder assembly is designed to hold an AECL C-235 capsule (refer to Registration No. NR-169-S-161 S). It is a cylindrical brass holder 1.47 inches long and 5/8 of an inch 0.0. The inner capsule (AECL C-235) is. held in place by an "0" ring screw. It has a removable end cap which provides approximately 1/4 of an inch of brass shielding. The assembly can be
-procured with an optional AECL model C-284 filter assembly containing a 2 mil thick tin filter.
LABELING:
?
The inner capsule is engraved with AECL, the nuclide, model number, and the source serial number. The outer source holder is engraved with AECL, the nuclide, the model number, and the^ source serial number.
DIAGRAM:
See attached drawings.
CONDITIONS OF NORMAL USE:
These sources would normally be incorporated in laboratory testing equipment such as bone mineral analyzers, etc. The use would normally be in clinical laboratory, industrial or other research laboratory environments under standard condition of temperature and pressure.
i
o REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-S-135-5 DATE: J;,'\ , ;984 PAGE 3 0F 6, SOURCE TYPE: Gamma / Photon Source PROTOTYPE TESTING:
Same as for C-235/C-236 gamma sources. By certificate dated May 24, 1972, the manufacturer claims a classification of C34334 for the model C-235 inner capsule in accordance with standards established by ANSI Committee N43-3.
EXTERNAL RADIATION LEVELS:
The manufacturer states that a source containing 3 Ci of iodine-125 would be expected to register the following readings:
2 (a) at 12 inches from the top surface of source C-235 = 2.9 R/h, (b) at 12 inches from the top surface of source / holder assembly C-281 through the unobstructed window and with shipping cap removed
= 215 R/h, (c) at 12 inches from the top surface of source / holder assembly C-281, foil filter C-284 installed and with shipping cap removed = 1.3 R/h, (d) in contact with the side of source / holder assembly C-281, foil filter C-284 and shipping cap installed = approximately 100 mR/h.
, - - ,- ._-r
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l REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SOURCE (Amended in Entirety)
NO.: NR-169-5-135-S DATE: ,rjh 1 ' ,984 PAGE 4 0F 6 SOURCE TYPE: Gamma / Photon Source QUALITY ASSURANCE AND CONTROL:
The manufacturer performs both destructive and nondestructive tests on the source. Weld quality is checked by destructive means. Each source is checked for leakage by a hot liquid bubble test within seven days of shipment, and each source is checked for contamination (both inner and outer capsules) by dry smearing the source. Activity limits for the smears are 0.005 microcurie on the inner capsule and 0.0005 microcurie on the outer capsule. The smear test is repeated after seven days or more and within seven days of shipment.
2 SAFETY ANALYSIS
SUMMARY
Based on our review of the information and test data contained in the references cited below, we conclude that the Model C-281 source design continues to be acceptable for licensing purposes. The basic source design was originally approved for licensing purposes by the U.S. Atomic Energy Commission in 1972, for the use of a maximum of one Curie of iodine-125. The increased maximum activity of 3 Curies of iodine-125 and the use of the additional radionuclides and their respective maximum activities listed in this certificate are not expected to have a deleterious effect on the source containment. Therefore, we conclude that the Model C-281 sealed sources would be expected to maintain their containment integrity for normal conditions of use and accident conditions which might occur during uses specified in this certificate.
4 REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALEb SOURCE N0.: NR1695135U DATE: August 01, 1972 PAGE 1 0F 2 SEALED SOURCE TYFE: Gamma Source MODEL: C-281 i
MANUFACTURER / DISTRIBUTOR: Atomic Energy of Canada, Ltd.
Commercial Products P. O. Box 93 Ottawa, Canada MANUFACTURER / DISTRIBUTOR:
i ISOTOPE: Iodine-125 MAXIMUM ACTIVITY: 1 curie LEAK TEST FREQUENCY:
1 PP,INCIPAL USE: Other CUSTOM SOURCE: YES X N0
REGISTRY OF RADI0 ACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR169S135U DATE: August 01, 1972 PAGE 2 0F 2 SEALED SOURCE TYPE: Gamma Source DESCRIPTION:
The AECL C-281 source and holder assembly is designed to hold an AECL C-235 capsule containing iodine-125. It is a cylindrical brass holder 1.47 inches long and 5/8 of an inch 0.D. The inner capsule (AECL C-235) is held in place by an "0" ring 1/4 inches 0.D. by 1/8 inch I.D. and a bottom cap attached to the body by a set screw. It has a removable end cap which provides approximately 1/4 of an inch of brass shielding. The assembly can be procured with an optional AECL model C-284 filter assembly containing a 2 mil thick tin filter.
LABELING:
The inner capsule is engraved with AECL, the nuclide, model number, and the source serial number. The outer source holder is engraved with AECL, the nuclide, the model number, and the source serial number.
PROTOTYPE TESTING:
2 Same as for C-235/C-236 gamma sources.
ISSUING AGENCY:
U.S. Atomic Energy Connission I
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