ML20198D872
| ML20198D872 | |
| Person / Time | |
|---|---|
| Site: | USA/9185/B(U)-96, 07109157, 07109156 |
| Issue date: | 12/03/1997 |
| From: | Cuthbertson T, Huddleston B INDUSTRIAL NUCLEAR CO. |
| To: | David Tiktinsky NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| IEB-97-002, IEB-97-2, NUDOCS 9801080292 | |
| Download: ML20198D872 (1) | |
Text
71 915G 71-9157 l C C.
7i.9185 i li W lNDysTRiAL NUCLEAR CO,INC.
4 Dewmber 03,1997 U. S. Nuclear Regulatory Commission Transportation Branch Office of Nuclear Material Safety and Safeguards NMSS Washington, D.C. 20555 Attention:
David Tiktinsky Room #6C7
Subject:
NRC Eulletin 97-02 10 CFR Part 71.73(c)(3)
Dear Mr. Tiktinsky,
In response to NRC Bulletin 97 C:. telephone conversation of November 13,1997 (with Tom W. Cuthbertson), fax transmittal dated November 14,1997 (with attachments), and telephone conversation of December 02,1997 (with Bill liuddleston), Industrial Nuclear Com;wny submits the following:
The documentation subraitted for th a pune:ure assessment test for the IR 100 Exposure Device JUSA/9157/B(U), the IR 50 Source Chancer [ USA /9156/B(U) and Overpack
[US A/9185/B(U)] (used for shipoing the IR 50 Changer and IR-100 Exposure), sent with the faxed transmittal of November 14, 1997, and here attached, meets the requirements of 10 CFR Part 71.73(c)(3).
Certification: We, Tom W. Cuthbertson (RSO) and Bill liuddleston (President) of Industrial Nuclear Company, attes, under penalty of perjury, that the documents submitted (as noted above) are genuine and te ate to the irons in question, to the best of our knowledge.
Thank you for your cooperation in this matter.11opefully, our response has met w4h your approval and will resolve this matter, liowever, should you have any questions or need additional inforri.ation or clarification, please contact the undersigned or Mr. Tom W.
/
Cuthbertson.
/
Sincerely.
,yF/Y h/Ao&& L Billliuddleston Tom W. Cuthbertson President RSO Enclosu r cc: Tom W. Cuthbertson 9001090292 971203 _
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11320 W4 ts Bhe8, $44 Ls;*Wro, CA 94 577 101 ($10' 3$2 64644
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1 FaH Transmittal Form To:
U.S. Nuclear Regulatory Commission FAXi301-415-8555 Washington, D.C. 20555 Roorn #6c7 (301)415 8523 Fas #:
From:
Tom W. Cuthbertson 14320 Wicks Blvd.
San Leandro, CA 94577 Fas (510) 357 1343 Office # (510) 357-1342 2515 Williams St.
San Leandro, C A 94577 Fas (510) 352 6772 Ollice # (510) 352-6766 Nuniher of Pages:
Fiflecil (15)
Onclaimg mver sheco
Subject:
NRC Bulletin 97 02 10 CFR Part 71.73(c)(3)
Coniments:
This correspondence is in response to NRC Bulletin 97 02 and our telephone conversation of November 13,1997.
Mr. Tiktinsky, please find attached documentation for the puncture assessment test for the IR-100 Exposure Device (USA /9157/B(U)] and the IR-50 Source Changer (US A/9156/B(U)] and Overpack lUS A/9185/B(U)]
used for shipping the IR 50 Changer.
INC feels that the auncture assessment test performed on the IR-100 (October 1990) and R-50 Changer meets the requirement of 10 CFR Pan 71.73(c)(3).
Ilopefully our response will allow you to resolve this mater to your satisfaction. Ilowever,if you are still in need of additional information or,
please contact Bill Iluddleston (will be in the Office on 11/17/97) or Tom W. Cuthbertson.
Thank you for your cooperation in this matter.
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oct bor 29, 1990 l
INDUSTRIAL NUCLEAR COMPANY Materials Laboratory No. M0103 2515 Williams Street Project No. 14543 San Leandro, CA 94577 Attention:
Mr. E. W. Iluddleston, President Subject Testino of Industrial Nuclear's Model IR100 Camqrg j
Type B USA /9157/Bful Serial #4005. submitud on 10/26/99.
Dear Mr. liuddlestone i
At your request, we have performed a free drop test and a puncture test on the camera sulunitted on 10/26/90.
Testing was performed
'j in accordance with Nuc'.Aar Regulatory Commission 10 CPR Ch.1 (1-1-90 Edition) S71.73 !!ypothetical accident conditions. The ambient air temperature throughout the test was approximately 70F.
The weight of the camera was 52.4 pounds.
Testing was witnessed by Mr.
E. W. Iluddleston.
l TESTING PROCEDURL7 1)
FREE DROP A free drop of the camera through a distance of nine meters (30 ft.) into a flat, essentially unyielding, horizontal surface, striki~t the surface in a position i
for which maximum d uage a axpected.
2)
PUNCTURE A free drop of the camera through a distance of one meter (40 inches) in a position for which maximum damage is expected, onto the upper end of a solid,
- vertical, g
cylindrical mild steel bar mounted on an essentially i
unylolding, horizontal surface.
The bar was 15 cm (six H
inches) in diameter, with the top horizontal and its edge i
rounded to a radius of not more than six mm (1/4 inches) f and of a length as to cause maximum damage to the camera,
(__.
but not less than 20 cm (eight inches) long.
The long
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axis of the bar was vertical.
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YE4&dY4b /2-3 97 1
2811 Adeline Street, P.O. Box 24075. Oakland. Califor nia 94G23 (415) 835 3142 SANTA CLARA
- C4Blo VALLEY ' SACnAMEllio
- MONTEnEY
4 Mr. E. W. Iluddleston, President Materials Laboratory No. M0103
' INDUSTRIAL NUCLEAR COMPANY Project No. 14543 PAGE 2 al 1)
Before the 30 foot drop test the camera was weighed and n
F photographed.
Damage sustained from the drcp was U
documented with photographs. Lock Box was broken of f and source was dislodged and thrown approximately 10 feet fror, camera.
See attached photographs (pages 4 thru 7).
2)
No puncture test was performed, camera failed 30 foot drop test.
LJ q
b INDUSTRIAL NUCLEAR COMPANY repaired the fillet weld around the lock box of the camera.
At Mr. Ituddleston's request a second test was performed on the camera (" Tial #4005) af ter the r]q ropair was made.
The second test was conducted using the same testing procedure.
Testing was witnessed by Mr.
E.W.
Iluddleston.
1)
Before the 30 foot drop test, the camera was weighed and photographed.
Damage sustained from the drop was r
documented with photographs.
The source did not become L
di=1od ed-see attached photos (pa9es 8 thru 12).
9 2)
Damage sustained from the puncture test is documented with photographs.
The source did not become dislodged.
See attached photographs (pages 13 and 14),
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' INDUSTRIAL NUCLEAR COMPANY Project No. 14543 PAGE 3 If you have any question regarding this report please contact the unde *stgned at (415)835-3142, Ext. 276.
Very n ily yours, TE T NG N/INEERS, INC.
ut [S~E E
D'n Watanabo Assistant Metallurgist DWagy Attachmonts
[ps, REVIEWED BY:
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and Quality Engineer (QU-2520) cca Mark Bautista, TESTING ENGINEEstS, INC.h4 Bob Gatowood, TESTING ENGINEERS, INC.
Mark Humbert, SEYFORTH S!!AW FAIRWEATHER AND GERALDSON E
Chris Kavalaris, TESTING ENGINEERS, INC.
Bill Keysor, P.E., TESTING ENGINEERS, INC.
John B. Martin, USNRC Poto Palko, TESTING ENGINEERS, INC.
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P.. W. Huddleston, President Materials Laboratory No. M0103 INDUSTRIAL NUCLP.AR COMPANY Project No. 14543 PAGE 14 gy, '
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CERTIFICATE OF COMPLIANCE dj a c'a n ton RADIOACTIVE MATERIALS PACKAGES
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Industrial Nuclear Company Industrial Nuclear Company Application p
l 2515 Williams Street dated December 23, 1981, as supplemented.
r San Leandro, CA 94577 Q., h... m h 8../.?
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The Model No. 1R-100 exposure device is. designed for.use as an exposure i
device, storage container, and Type B shipping container for radiographic
'I sources in special form. The Model No. lR-100 exposure device measures j
8.875' inches long, 4.5 inches wide, and 8.5 inches high.
The radioactive l
source. assembly is housed in Zircalloy or titanium *S" tube.
The "S" g
tube is surrounded by depleted uranium metal as. shielding material. The q
depleted uranium shield assembly is encased in a stainless steel
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housing. The void space between the depleted uranium shield assembly and i
the inner container is filled with a rigid polyurethane foam.
Tlie gross
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weight of the. exposure device is 53 pounds.
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(3) Drawings "i.
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The packaging is constructed in accordance with Industrial Nuclear Company
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Drawing No. lA, Rev. 2, dated November 4,1992 and IB, Rev.1, dated June 15, 1992.
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Nge 2 - Cartificate No. 9157 - Revision No. 6 - Docket No. 71-9157 I
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(1) Type and form of material
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Iridium 192 as sealed sources that meet the requirements of special form l
radioactive material.
l (2) Maximum quantity of material per package i
4 120 curies d
6.
The source must be secured in the shielded position of the packaging by the
'T shipping plug, source assembly, and locking device. The shipping plug, source
$1 assembly used must be fabricated Sof'm'aterials capatle of resisting a 1475*F fire environment for one-half hour and maintaining. heir positioning i
function.
The ball. ! top of the source assembly must engage the locking i
device. The flexible cable of the Jource assembly' and shipping plug must be of sufficient length and diameter to provide positive positioning of the source in the.' shielded position.
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,g The name pla'te an7'he-exposure device must be'. fabricated of materials capable 7.
t of resisting'.the fire test of 10 CFR Part.712.and maintaining its legibility,
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In additiorito the requirements, of.SuSpart Glor 10 CFR Part 71, each pa age must meetethe acceptance tests and maintenance-program, and shall be c ated and prepared for shipn.entin accordance ~with.the operating procedures in the application document entitled "0 erating Procedures, Acceptance Test, and P
Maintenance, Program,-" M -R] vision:1,; dated November 4,'1992, as suppleme December 15,1992.f.jbi'0{ 10}t(! t !~ (!y$b.d.-y"
,D The packaging authorized by this{, certificate is hereby approved for us bt(t n
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ihe general 1icense previs!an.v'of.10 CFR 971.02.
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Expiratinndate:/ January 31, 1998.N
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P BEFERENCES p Industrial Nuclear Company application..!-
'~ Y 4-afated December 23, 1981.
Supplomants dated: May 28, 1982; October 13, 1983 (twe letters); November 26, 1990; February 22, and April 26, 1991; and March 20, u ne 25, September 4, November 4 and Decen. Der 15, 1992.
s FOR Tile U.S. NUCLEAR REGULATORY COMMISSION Ni k
u Charles E. MacDon W, Chief Transportation Branch Division of Safeguards gg3 and Transportation, HMSS
$h,I Date-f
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INDUSTRIAL NUCLEAR COMPANY (415) 349-6307 1124 Chess Drive, Foster City, CA. 94404 e
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12-23-81 I
C.
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MACDOtJALD, CHIEF tJUCLEAR MATERI AL SAFETY a SAFEGUARDS i
tJUCLEAR REGULATORY COMMISSIOtJ WASHItJGTOri D. C.
20555 h
DEAR SIR:
INFOR;1ATIOt1 FOR THE APPROVAL OF OUR RADIOACTIVE Ef4 CLOSED IS MATERI AL SHIPPItJG COtJTRItJER-MODEL 50, AS A TYPd "B"
PACKAGE 8
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WHEN IT COtJTAlf45 120 CURIES OF IR-192, NHILE IT IS COtJTRItJED Itd A METAL DRUM OVERPACK.
ItJFORMATION COtJTAItJED HEREItJ FOLLOWS THE OUTLItJE PER THE 10 CFR 71.21.
PLEASE fJOTE THAT WE HAVE SUBMITTED THE APPLICATIOt1 FOR THE l
IR 100 EXPOSURE DEVICE AT THti SAME TIME IN ORDER TO y
MODEL SIMPLIFY THE APPLICATION REVIEW. THE COtJSTRI.sCTION OF BOTH DEVICES IS tJEARLY IDErJTICAL.
YOUR FROMPT ATTEtJTION TO THIS APPLICATION WILL BE GREATLY APPRECIATED.
SINCERELY,
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1 10 CIlt 71 APPENDIX-A BY DATO 3.
HEAT A10*F (TRVED FOAM G 250-F for 3 HOURS) mM
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COLD-f00LII TO-40*7 77 a / 2 /.,
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PRESit'RE- 0.5 x 3 HC-15" 1r. (Vacuum) i46
'8 /* / U (TESTED FOAM SAMPLE AS USED ON IR-100 WITH Fr,1"DICATION OF 10 CFR 7_1 AP"DiDIX-B dan ics.)
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VIBR.a.(ION-PACI 4E SUBJECTID TO A "C" FORCE RANCE OF.075 thru I M I 8'/2/ O IUTE: APPLY TEST SEQUEN(.IAIM TO DE!'EMINE THE CUMULATIVE EFFECT.
15 C.
FOR tumr F-10-45-10 2X THE RADIATION FROM A 126 CURIE IR-192 SOURCE PER 10 CFR 71.36 DISPI '.CD4EhTa 15in., APPROX.Tmin.RANCECYCLE a 1 & 2 MUST MEET THE FOLIDWING CONDITIONS AFTER FACH TEST:
5.
WATEE SPRAY-SPRINELER 30 sia. (10 DAMACE)
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MAX 7 MIDI OF 1000 ar/hr @ 3 FEET FROM PACKAGE StfRFACE.
6.
FREE OROP-1%-2% HOURS AFTER STEP 5. PACKAGE DRDPPED 4 f*T W
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DATE 2.
NO RADIOACTIVE MATERIAL MAY BE RELEASED.
ONTO +'" THICK STEEL PLATE ON CONCRETE 3100R l
TEST:
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FREE DROP (30 FT)-(IUR MAX IMPACT & DAMAGE, DROP PACKACE ngog I
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$0 THE CDTTER OF CRAVITY (C.C.) PASSES THRU THE IDCK SO AS A L-g 4,IM -2
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PDIETEATION-1k" DIA. 13 LB. STEEL BAR WIT'l HDtISPHEkE DdDS I N l/3/O
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~DO SIDE IDCK NO IDCK BODY DAMACE NO IDCK BODY 3/16" DEtk D'ENT AT POItt!
3f16"DEEFEDfr AT POINT 1/8'DE F CROVE DDfr, U
DAMAGE OF IMPACT OF IMPACT NO WEID DAMACE NO OTHER D M E DO OTHER DAMACE C.
THERMAL-(1) EXPOSE PACKACE TO 1475*F.
F ok 30 min., cool NG SHIFT of SOURCE g NO SHIFT OF SOURCE l NO SHIFT OF SOURCE IN STILL AIR.
(1ESTED BY METALS IIEAT TREATINC)
RESULTS: NO BURNED-THRU ARE45 PE.t LTR 9.
COMPRESSION-SU-5 x 70-350 for 24 t.our W T l rig /L Z(fM*l C.
RADIATION-(2)PACKACE TESTED 6) 120 CURIE IR-192 SOURCE AESULTS: f JNCREASE IN RAD.ATION LEVEL. ALL SULACES WERE l-I r(DW 2(QM.tLlft.
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i The Model No. IR '.50 shippin'g con' aTne6.ikde' signed fo Jise as a source l'
t i
changer,, storage rontainer, and Type'B shipping 4ontain'er for i
j radiographic sour'cet in'specialEform. The Model No. IR-50 source changer
[
,g measures 8.875 inches long;;4.5 inches wide,.and 8.5 (nches high.
The p
radioactive. sourc<t issembly~ is1 housed in Zircalloy or~ titanium "S" tube, p
q The"S" tube'issurroundedby'depletedur'aniummeta14ssl4'11ng p
s n
material. The depleted uranium shield assembly isCencaset a stainless b
9 steel housing. 9The void spa'ce betdeen ths' depleted'hranium shield j
assembly and the' inner container is filled with..a} rigid polyurethane l
- foam. The 45 pound source changer is centered.by plywood supports within 4
g g
a 10 gallon (min 20 gauge). steel drum with a 12-gauge steel closure ring.
p i
The gross weight of the source.. changer and overpack is 70 pounds, e
l (3)
Drawings l
l i'
The packaging is constructed in accordance with Industrial Nuclear l
Company Drawing Nos.: 2A, Rev. 1, dated November 4, 1992; 2B, Rev. 1, n
y dated August 31, 1992; 50-4, Rev. 2, dated November 4, 1992; and 50-4(A),
i Rev. 2, dated August 31, 1992, i
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i M
i W
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H i
4 i
i F
r i
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? DJ 2 6' l
\\
n g
k m
peacamt -
m'I"FE"IM"2".1"KNM
.ac.s ma.mm xa.
l CcHotTl:Ns (cru,unved)
(
Page 2 - Certificate No. 9156 - Revision No. 4 - Docket No. 71-9156 I
l (b) Contents i
(
(1)
Type and form of material l
Iridium 192 as sealed sources that meet the requirements of special form radioactive material.
(2)
Maximum quantity of material per package u
l 120 curies l
0.
The sources must be secured in the.chielded position of the packaging of the y
i shipping plug, source assembly, and locking device. The shipping plug, source e
i assembly used must be fabricated of materials' capable of resisting 4 1475'F i
i fire environment for oneihalf hour and maintaining their positioning function.
I I
The ball stop of the, source assembly must engage the locking device.
The I
l flexible cable of the source assembly and shipping plug must ba of sufficient f
i length and ditmetehs.to provide positive positioning of the source in the i
g.
shieldedpositio,n.]
1 i
I I
7.
The name plate on,. overpack'n'ust be fabricated of materials capable I
I of resisting the fire test of 10 CFR'Part 71 and. maintaining its legibility.
I l
The two vent holes in the side of the overpack must be covered with tape or l
4 rubber (plastic) plugs to. prevent entry of rain water.
y y
g.
g y
I 8.
In addition to the requirements of Subpart G of.10 CFR Part 71, each package 1
I must meet the acceptance tests and maintenance program, and shall be operated i
3 and prepared for shipment in accordance with the operating procedures in the 1
l application document entitled " Operating Procedures, Acceptance Test, and j
s Maintenance Program," Rev,ision 1, dated November 4,1992, i
I I
i 9.
The packaging authorized by this certificate is hereby approved for use under i
I the general license' provisions of 10 CFR 571.12.
1
[
i f; i
10.
Expiration date: January 31, 1998.
l i
p i
p i
U ERENCES **
.g i
i I
Industrial Nuclear Company application dated December 23, 1981.
I l
l i
Supplements dated: May 28, 1982; 0-tober 13, 1983; and March 20, June 25, l
i i
September 4, and November 4, 1992.
I i
I i
I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I
b I
Charles E. MacDonald, Chief I
l Transportation Branch E
i Division of Safeguards and l
1
-Transportation, NMSS i
I i
I JAN 7 1993 i
I Date:
l ul m-------.--..-_...----..-.a
.. +
.=. u - :-
c
- s -._
y I
u.a. Nuol. EAR REGUMToRY COMMISSION I
une pone ese I
a=
CERTIFICATE OF COMPLIANCE I
I
C'""
FOR RADIOACTIVE MAltRIALS PACKAGES I
1.s CSAT'FsCATI NUNCLA e.REYt&lON NVW.LM s PACAAQt lOENTIF6CATtON NUWeER e PAGE NUWeER
- e. Toi AL NUMBER PAole l
. 9185 3
USA /9185/B(U) 1 2
g I
t empus4.s 9
l
- e. This certif6cate le te6ved to certfry met the packaging and cot Snts described in hem 5 below.mwts the applicab6e safety etendarde set forth inTtt6e to, Code
. I l
of F9deral ReOulations, Port 71.* Packaging and Trenoportation of Radioactavo Meterlav I
- b. This certincete does not releeve me consignor frt-m compliance with any requeroment of the rogdet6one of the U.S. Deperiment of Transportet6on or other I
applicabio regulatory agencias, inc!vding the government of any country through or into which the pechage will be trenoported.
I I
- "miE Thd.*o*<" J*" * ' ' **'" "'Mfe" ^7c^ff 8r**cL%^TAEarm i
I Industrial Nuclear Company Industrial Nuclear Company application I
l 2515 Williams Street dated October 13, 1983.
l San Leandro, 'CA 94577 i
e g R R E G,e 71-9185
- i i
U/
I i
Ay e.ooexrTNuw Em I
I e coverf.oNo V-wq I
This certificate le conditionet upon.fuhliling equirements of 10 CFR Port 71. es appl 6 cable, and the tions spectfled below.
l
'(a)
Packaging Y
O l
(1) Model No.
P-1
)
(2) Descriptb 2
f)
I Protect overpackk odel
,J -10 e ure devi b The everpack consist 'Trf an,o'pter tonta$er whRhT'eMVelde.Qeams.2nd a 12-gauge ATO' galjon oppshead steel drum i
s having a*(ninimunt 20-ga'ug'u%ocyft e
-cov I
clam -ri?ig' typep[ff ead clo dJ ET
{'4ond p'xpopure qqyJce is centered I
I t
hegossjweighf;;pftheexposure by p ywood luppo,r Ithirt.$'o )I N
y device anti erpa 78
(3) Drawings Y "h
(9 I
The overpack oostructed in ecNrdancewith p strial Nuclear Company 10Q 4, Rev. 2, dated Novemberyh1992; and 100-4(A),
- l l
Drawing Nos.:
Rev. 2, dated August 3. 1 l
l l
I I
I I
]
7 y
I I
-l I
I 1
I I
I y
fhY$
i 1
I
r n.____________________
us meAn uma couuim
! L'*"""
cowomous(conunu a/
o l
Page 2 Certificate No. 9105 - Revision No. 3 - Docket No. 71-9185 I
I I
I
- I (b) Contents I
f I
I
{l (1)
Type and form of' material l
Iridium 192 as sealed sources that meet the requirements of I
special form radioactive material.
I I
I I
(2)
Maximum quantity of material per package l
120 curies I
l I
6.
ThesourcesmustbecontainedwithintheNg(elNo.IR-300packagingin i
r j
sccordance with Certificat
}dpitink $3 5.
l l
7.
The name plate on the k must be fabricater d materials capable of resisting the fire, t of 10 CFR Part 71 and man ing its legibility.
i i
The two vent holes @Ogs to prevent entry of rain water, i
Jthe side of the overpack must be ered with tape or l
rubber (plastic) f(
p I
I In t.ddition to NO re h a ts of Subpart G o I
8.
Pa 1, each package I
must meet the d(ce)tanchhs and maintenan am, and hall be operated l'
and prepared r,siipmen.
hrdCceWit erating edures in the i
3 t
i application d ument enti Qperg glPr
, Accept Test, and i
i Maintenance P ram," Re
(, dj Novy b'e 1992, as-ppplemented i
/
l
- ~
December 15,pS2.
- g i
9.
The packag n (r9 thor M
Lih
'apprhdforuseunder the genera ic ep s
1 i ( I?..
i l
i
- 10. Expirationdate:panuai g
/
REFER,NCE l
i Industrial Nuclear Company ication dated December 23 81.*
I Supplements dated: May 28, 1982*
cthr hB3 wo letters)*; April 26, 1991; and March 20, June 25, September 4, Novlmb@frN, and December 15, 1992.
-l
' l j
i i
I f
I I
I
- See Doc.ket No. 71-9157.
l I
I l
FOR THE U.S. NUCLEAR REGULATORY COMMISSION I
l
'?
I Charles E. MacDonald, Chief l
Transportation Branch i
Division of Safeguards and i
Transportation, NMSS j7 I'
Date:
s.
I i
-