ML19249A611
| ML19249A611 | |
| Person / Time | |
|---|---|
| Site: | 07100336 |
| Issue date: | 07/02/1979 |
| From: | Curtis F CLEVELAND X-RAY INSPECTION, INC. |
| To: | |
| Shared Package | |
| ML19249A607 | List: |
| References | |
| NUDOCS 7908240048 | |
| Download: ML19249A611 (7) | |
Text
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' t.m Cleveland X-Ray _Inspe,ction Inq.
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(Name of Licensee) 9...
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35-15205-01 W '"
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(License f:umter)
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FOR COMPLIANCE WITH 10 CFR PART 11, APPECIX E f
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Organization
- F ai The final responsibility for the Quality Assurance (QA) Program for Part 71 Requirenents rests with Cleveland X-PJV In ge.ction. Inc.
a (Nane of Licensee)
Oesign and Fabricatio,1 shall not be conducted under this OA Program.
t The QA Proy am is implemented as shown on the attached organization
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'1 chart.
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The Radiation Safety Officer is responsible for overall adm;nistration
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of the program, training and certification, document ontrol, ano
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auditing.
m The Radiographers are responsible for handling, storing, shipping, inspection, test and operating status and record keeping.
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Quality Assurance Program i '
The management of 3:gy n
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=stablishes and implements this QA Program Training, prior to M..,,kw 2!W. o
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engagement, fer all QA functions is required according to written procedures. QA program revisions will be made aCCordino to written procedures with management approval. The GA Program will ensure that all defined QA procedures, engineering procedures, and specific provisions of the package design approval are satisfied. The QA
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Program will emphasize control of the characteristics of the package which are critical to safety.
The Radiation Safety Officer shall assure that all radioactive material sh pping packages are designed and manufactured und?r a OA Program approved by Nuclear Regulatory Comission for all packanes desioned or fabricated after July 1, 1978. This requirement can be satisfied by receiving a certification to this effect from the nanufacturer.
3.
Document Control All documents related to a specific shipping package will be controlled through the use of written procedures. All document charces will be performed according to written procedures approved by ranagement.
The Radiation Safety Officer shall insure that all QA functions are conducted in accordance with the latest aoplicable changes to these documents.
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79082 40M5 -
Gama Industries Form #604-/001-0012/79
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Handling Storaae and Shipping Written safety procedures concerning the handling, storage and shipping of packages for certain special form radioactive material will be followed. Shipments will not be rtade unle.s all tests, certifications, acceptances, and final inspections have been coPpleted. Work instruct-ions will be provided for handling, storage, and shipping operations.
^ '
Radiography personnel shall perform the critical handling, storage and shipping operations.
5.
Inspection, Test and Operating Status Inspetti test and operating status of packages for certain special form radiv.ctive material will be indicated and controlled by written
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procedures. Status will be indicated by tag, label, marking or log entry. Status of nonconforming parts or packages will be positively s
maintained by written procedures, aJp Radiography personnel shall perform the regulatory required inspections Je t.-
and tests in accordance with written procedures. The Radiatis; Safety Officer shall ensure that these functions are perforned.
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6.
Quality Assurance Records s
s Records of package aporovals (including references and drawings).
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procurement, inspecticns, tests, operating logs, audit results, personnel s.
training and qualifications and records of shipments will be maintained.
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4 Descriptions of equipment and written procedures will also be maintained.
These records will be maintained in accordance with written procedures.
The records will be identifiable and retrievable. A list of these
- "*ug records, with their s' 3 rage locations, will be naintained by the Radiation Safety Officer.
7.
Audits A<.
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Established schedules of aucits of the QA Program will be perforned using
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' 'j written check lists. Results of audits will be maintained and reported
~g 71 to management. Audit reports will be evaluated and deficient areas corrected.
i The audits will be dependent on the safety significance of the activity
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being audited, but each activity will be audited at least once per year.
d Audit reports will be maintained as part of the quality assurance records.
Y st Members of the audit team snall have no responsibility in the activity b'-
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Datt bgrfatere and Title ofWsponsible Licensee Official
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Printed hace and litle of kesponsible
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Licensee Address
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y Gama Industries Form #604-7001-001 2/79 1
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QUALITY A35'J ANCE PR09AM CE M i?ATICN CH D T FC?
C risv t InaT-nfvT-mecthe Inc.
Name o Licensee /
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35-15205-01 (License X -foer)
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-FOR COMPLIANCE WITH 10 CFR PMT 71, APPENDD E g,
Fant t e_DJ r tis
, President
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Operations Manager Radiation Sa fety Of fice -
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_ Copy of firaa== Attached:
Radiograpner
_~Ai Radiographer s
0 Q g s,;jy Radiographer
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DESCRIPTION OF RESPONSIBILIT_Y d
1.
President - General management of the company.
2.
_ Operations Manager - Responsible for opera tions control of the company, supervision of employees, cost control, job assignments, personnel relations, training.
3.
Radiation Safety Officer - Responsible fJr overall administration of the radia+,' ion safety program (including Quality Assurance), gersonnel radiation safety training and certification, document control, and auditing of the radiation safety program.
4.
Radiographers - Responsible for using, storing, shipping, inspection, testing, operating status, and record keeping of radtoisotope sources and devices in accord with written procedures of the company as approved by the Operations Manager and Radiation Safety Of ficer.
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MATERIALS LICENSE Ar.'erxhtent.Ud. 07 n..
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Act of 1974 (Public. Law 93 c
,Purnant to' the Atomic Energy Act of 1954. as amended, the Energy Reorganizationr
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.l438Dxodl,TitleMO.' Code of s'ederal Regulations n
licensee to Mstatements'and' representations heretofore inado by's>ource',icensee, a the l and special nuclear material. designated below: lolu,e such e'ceiveh.gquiritipossess and transfer byproduct.1 d belcw; to Miver or transfer such material to persens authorized -
.,'ruterial]irJ he,)urposeis) and~st the placels) designate and to import such byproduct s'nd source l
"jid -recelv<i'li'da.accordance.w'ith the regulations of the applicable Part(s)'h. oa
y.Wa' men'ded.Md?is subject. tos a11 applicable rules,'r'egulations and orders of,the N
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' h f' vft r.in effe.c.t and to any conditions specified beEw.
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No single.coIi.rce E
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. cxceed 100' curies 75'~C.4[.fridium192
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2 of ' 4 - Pages U. S.~ NUCLEAR REGULATORY COMMISSION Page p**M,s-~'
NATERIALS LICENSE a,.
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Supplementary Sheet 2'
35-15205-01 1
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License Number
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5,fByproduc't, source, 'and/or
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- 8. Maximum amount that licensee
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may possess at any onelime
- D speial 'nucleimaterial' ~
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under this license
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No single cource to yM; H.* Cesium 137'-
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Mode) 72602.Se. aled exceed 100 millicuries 4@N? %M
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Garra Industries 3
I. I No: single source to 2
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Si d % del VD(HP) Sealed '
exceed 225 millicuries Tfi *.' ; < "iy.C,. u!N ', M.'Y A g.p,4. 7-M 1 % -- V.;"2 *..: ' f;i _
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-Gulf Nuclear, Inc/ Model 20V exposure ~ devices for -industrial d$$ ' i radiography zarid in. Gulf-Nucledr, Inc. 'Hodel U-110A' source changers for 4 E.stbrage and> replacement of sources.
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. For:,use ih Source Production and Equiptent Model 2 T exposure devices for@.
jY'W]e'/ ir.dustrial' radiography;and irpSource Production Equiprent mdel C-1 sourc f
6~?.g.'Tchangers for storage.and replacement of sources.
gWA Cr " Eociuse 'in-Gamma.; Industries mdel 35 exposure devices' for industrial.
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! h for. storag'e.
jffpgahd@g'r'aphy a'rx3 in Garra Industries Model C--10 source c angers.
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. radio l
eplacatent of. sourcesi ~.y v
9D.Z Fot use:in' Gulf Nuclear,'Inc.';Model. 20( exposure devices'for. industrialW -
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,._ r;,railiography.alid -in Gulf Nucleah Podel U-110A source changers for storage and 9-
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"' '? %,' replacate'nt of ' sources.
jor use'in-Sotirce Product and'Equij;rtent Model 2-T exposure devices for
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m industrial' radiography 'and in Source Produc' tion and Equirent-Model C-1 source 1
~If/?9;>. changers;for storage.and 'replacment of sources.
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For.usefin Source PEoduction and Equiprent Model SPEC--Check % del I'~eximsure
-devices.for' industrial; radiography.
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'. _^.. G u Ebb use in. Gulf Nuclear, Inc. 'Model 10X Pipeliner exposure device for
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industrial rddiography.. ' ' '.
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- ' Poi'. use inIbchnical. Operations. Model 726 reeter calibratiort kit for calibration O
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of' survey ~ instruments.
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For use in Gam:ra Industries Master Minder Model No. l' to control the motion of f"~
x-ray crawlers within pipelines.
s CONDITIONS
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.10.
U :ps: a rnaterial may be stored at 909 West Osage, Cleveland, Oklahoma. Licensed
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E rratuial shall be used only at tarporary job sites of the licensee anywhere in the United States where the Nuclear Regulatory Ccmmission raintains jurisdiction j~-
for regulating the. use of licensed material.
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MATERIAIS LICENSE U..F@i$
CDNDITIONS
' Supplementary sheet ucense Number _ 35-15205-01 Docket or
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Reference No.
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Amendment No. 07' dN, ' lb 3 khe licensee shall comply with the provisions of Title 10, Chapter 1,
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- .Qode of Federal Regulations, Part 19, " Notices, Instructions and Reports to
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Norkers; Inspections," Part.20, " Standards for Protection Against Radiation,'
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and Part 34, " Licenses.for Radiography and. Radiation Safety Requircrents.for q ",_.
< Radiographic Operations."
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@_ k'.'4 5,# $ perform tests.for' leakage or contamina r;'12. '!A.'
Pursuant to Section '34.25,10 CFR 34, the licensee is authorized to -
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-dated'May.23,i1978 as7dnerbed Septaber 28,;1978..
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test required by Section 34.25(b),
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.e pht.l%.. '10 CEWl'34,.such requird5ent does not4 apply to rMiography sources that are stMe4;an3(not lieing us~eh he' sources excepted frmithfs test; sh'all be 4M?f t
!#@$.,e.?.M:fM2 nest'o'd for leakage pr;i'o'reto ~any,'usewr transfer to
-q....g.ey[hkTe?6e.en.ll. eak test.!'i(within six months' prior.. ts-thsidate: of Juse or
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M wjediogra@" ~ sources'4h accordance,with Section 34.2,5 of.10 CFR. 34.'
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licensee is" authorized.toereceive, pssess,fand.usegealed sources of?
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& aIridium;192:cr.: Cobalt-60 whdre the rodioactivity exceeds the maximum amount of C M M 'e,;ijlsdi'oactivi.tyJspecified in Itm 8 of 'this license provided:-
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h.YY,%.. Q p j . ; _., ' ' ?MW.t'Such possession' does dlot exceed lthe quantity
,.#g.7j{,@..;3.~N.bf.cors.than.'20%'forIrldium192'or:10%forCo
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W?@BU Jecordsr f the'.tlicensee show that no more.than the maximumfamount of o
C.' ~.N$6M@Dadioac.tIiv,it' ?'per source'specified i' Itcm 8 'of thcalicense was ordered
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- from ',the ~ supplier or,tr.Tansferor. of' the byproduct 7::aterial';"and n4., '_ 9....,.,
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, containers do.not excedd thoserspecified in Section 34.21,10i CFR 34,..
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of Source Material," the licensee is authorized to pssess, use, transfer, and import up to 450 kilograms of uranium contained as shielding *raterial in the
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radiographyiexposure devices and soucce changers authorized by this license.
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- 15. De licensee may transport licensed raterial or deliver licersed raterial to a carrier for transport in accordance with the provisions of Title 10, Code of Federal Regulations, Part 71, " Pack.-ging of Radioactive Material For Transport."
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U. S. NUCLEAR REGULATORY COMMISSION Page ' 4 of 4 Pages
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MATERIALS LICENSE D'C:. ^i e-35-15205-01 Supplementary Sheet License Number 5 J.
CONDITIONS Docket or Reference No.
,(contint ad)
Amendment No. 07
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. L,,.'e.16+' Except as specifically provided otherwise by this license, the licensee shall possess and use licensed raterial described in Ite.s 6, 7, and 8 of this license l]W'. N;. Tin accordance with 'statments, representations, and procedures contained
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28,, 1978.-*.
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