ML20057D705
| ML20057D705 | |
| Person / Time | |
|---|---|
| Site: | 07100775 |
| Issue date: | 10/05/1993 |
| From: | LUKINS & ANNIS |
| To: | |
| References | |
| NUDOCS 9310050225 | |
| Download: ML20057D705 (7) | |
Text
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10CFR71 OA PROGRAM r
B & G INSPECTION i
1.
Organization The final responsibility for the Quality Assurance Program for Part 71 requirements rest with B & G Inspection. Design and fabrication of radioactive material shipping packages shall not be' conducted under t.his Quality Assurance Program. The Qualiti Assurance Program
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is implemented using the following organization:
" ORGANIZATIONAL CHART" OWNER & MANAGER R.S.O.
Denny Guerrero ASSISTANT R.S.O.
Jerry Waggoner Kenneth White RADIOGRAPHERS ASSISTANT RADIOGRAPHER The Radiation Safety Officer is responsible for overall administration cf the program, training and certification, document control, and auditing.
The Radiographers are responsible for handling, storing, shipping, inspection, test, operating status and record keeping.
2.
Quality Assurance Program The management of.B & G Inspection establishes and implements this Quality Assurance Program. Training for all OA function, prior to engagement in these functions, is required according to written procedures. QA Program revisions will be made according to written procedures with management approval. The QA Program will ensure that all defined Oc procedures, engineering procedures and specific provisions of the package design approval are satisfied. The OA Program will emphasize control of the characteristics of the package which are critical to safety.
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9310050225 931005 fT PDR ADOCK 071*****
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i The Radiation Safety Officer shall assure that all radioactive material shipping packages are designed and manufactured under a Quality Assurance Program approved by the Nuclear Regulatory Commission for all packages I
designed or fabricated after 1 January 1979. This requirement can be satisfied by receiving a certification to this effect from the manu-facturer.
3.
Document Control M1 documents related to a specific shipping package will be controlled through the use of written procedures. All document changes will be performed according to written procedures approved by management.
4 The Radiation Safety Officer shall insure that all QA functions are conducted in accordance with the latest applicable changes to these dccuments.
4.
Handling Storage and Shipping Written safety procedures concerning the handling, storage and shipping of packages for certain special form radioactive material will be l
followed. Shipments will not be made unless all tests, certifications, acceptances, and final inspections have been completed. Work instruc-tions will be provided for handling, storage and shipping operations.
Radiography personnel shall perform the critin' handling, storage and shipping operations.
5.
Inspection, Wst and Operating Status Inspection, test and operating status of packages for certain special form radioactive material will be indicated and controlled by written procedures. Status will be indicated by tag, label, marking or log entry. Status of nonconforming parts or packages will be positively maintained by written procedures.
l Radiography personnel shall perform the regulatory required inspections and tests in accordance with written procedures. The Radiation Safety Officer shall ensure that these functions are performed.
6.
Quality Assurance Records Records of package approvals (including references and drawing),
inspections, tests, operating logs, audit results, personnel training and qualifications and records of shipments will be maintained. Descrip-tions 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 records, with their storage locations, will be maintained by the Radiation Safety Officer.
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Audits i
Established schedules of audit.s of the Quality Assurance Program will l
be performed using written checklists. Results of audits will be maintained and reported to management. Audit reports will be evaluated and deficient areas corrected. The audits will be dependent on the safety significance of the activity being audited, but each activity will be audited at least once per year. Audit reports will be maintained i
as part of the quality assurance records. members of the audit team shall have no responsibility in the activity being audited.
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i Mr. Charles E.
MacDonald, Chief Transportation Branch.
Division of Safeguards and Transportation Nuclear Material Safety and Safeguard United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. MacDonald,
In accordance with 10 CFR 71.72 (c). (3), _3 n n incpnneinn f
Louisiana License #LA-70BO-LO1 requests to be registered as a user of Amersham Corporation, Model_G;Uj63 '
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-i Package identification Number USA / 6717 /B(U), under terms of certificate of Compliance Number 671'7 issued to Amersham Corporation, Burlington, MA Sincerely,
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J DEPARTME11T OF E13VIR0!!MEliTAL QUALITY OFFICE OF AIR QUALITY AllD RADIATIOli PROTECTIOli j
RADIOACTIVE MATERIAL LICENSE IiWDXhTIO51 Pn01(WNXOEl DXVIOZO71 P.O. DOX 02135 DhTOTl R00W, LU0fx0ENH% ~/0096-2135 U& G Inspection LA-7050-LO1 February 28, 1995 Route 2, flox 130 Ilush Road AMffffDMFIFT NUHitRH FPRVICUS AaODUDf1DerS Delhi, Loulslana 71232 Initial lut 1siin.E' i c<;Uf:D f URCU41T TO AND IN ACCOPCANCE WITH Application 4
Attention:
Benny Guerrero sianto ny,
- cAn, Benny Guerrero January 29, 1993 miE m.cr ir,idiinEsiis, u w t e m,.n c. e. ex,s.m. m ic.
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i i., c ;.,,<:c c u r rei r: Ai. r4 +n- - r nes icai. st a r e Atiruoeiizio uss Ir 192 Any 100 Ci Amersham Model Gamma Industries Industrial 848, 89911, Model Century S Radiography A-1-A; Spec Model G-1F, G-3F; Ill Model 22 Ir 192 Any 100 Ci Amersham Model Gamma Industries Industrial 848, B9912, A-2-A; 11odel Century SA Radiography SPEC 11odel G-3F; 111 Model 88 Ir 192 Any 100 C1 Amersham Model SPEC liodel 2-T Industrial 89911, 848, A-1-A, Radiography A-2-A; SPEC Model G-1, G-1F, G-3, G-3F, Ill Model 2, 22, 8,
88 Ir 192 Any 100 Ci Amersham Model Amersham Model Industrial A424-9, 2006600009; 660 Radiography g
SPEC Model T3, T5, T5F, T7, T10; 111 Model 7 Ir 192 Any 100 C1 Amersham Model Amersham Model Industrial A424-9; RTS 660 System (660 A, Radiography Model 701, 702 660 B, 660 AE, 660 BE) 010069 k
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Gust ave von nodungen, p.E
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f DEPARTHEllT OF ENVIROliMEllTAL QUALITY OFFICE OF AIR QUALITY AND RADIATIOli PROTECTIO!!
RADIATIO!I PRoTECTIOli DIVISION BATON ROUGE, LOUISIANA 70084-2135
-LICDMEE LICDME thJMPER AMENDMENT tl0F EMr!kATION DME
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LA-7050-LO1 Initial Februaiv 28, 199 B & G IJ1soectio11_
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n The source exchange and storage devices listed below are authorized for use in accordanc e
with the licensee's radiological Operating and Emergency Procedures:
1 Gamma Industries Source flodel C-10; SPEC Exchange i
tiodel C-1; Amersham and Storag i
11odel 650
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i 1.
A.
lladioactive material shall be stored at B & G Inspection, Route 2, Bush Road Delhi, Louisiana.
i B.
Radioactive material shall be used only at temporary jobsites of the license in Louisiana.
Prior to operation at temporary jobsites, the licensee shal comply with applicable provicions of other regulations of the Department e i
Environmental Quality, and obtain all applicable state and local permits, e
C.
This condition does not prohibit use in other Agreement States and state under the jurisdiction of the U.S.
Nuclear Regulatory Commission unde reciprocity procedures which may be established by an Agreement State or th -
U.S.
Iluclear Regulatory Commission.
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2.
This license does not authorize underwater radiography.
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Pursuant to Section 575.A. of the Louisiana Radiation Regulations, the license may permit an individual to act as a radiographer provided:
A.
Verification of satiafactory completion has been received from a perso approved by the Division, an Agreement State, or the fluclear Regulatot Conuniss ion to conduct a radiography training program which meets tb requirements equivalent to Section 575.A.1.
If verification cannot b received, then the licensee may accept verification from the holder of license issued by the Division, an Agreement State or the Nuclear Regulatot Commission that the individual has been employed as a radiographer as define by Section 503; and D.
The individual has received instruction and training which meets th requirements of Section 575.A.2.
and 3.
as specified in the licensee' Operating and Emergency Procedures; and C.
Appropriate records are maintained which demonstrate the individual has me the above requirements, and Form DRC-20 has been filed with the Division.
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D On-the-job training at temporary jobsites shall be under the direct persona i
supervision of the following instructors:
I!!STRUCTORS Benny Cuerrero Jerry Waggoner i
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Gustave von Bodungen, P.E o
j ms w m es Assistant Secretary February 8, 1993 2
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i DEPARTHENT OF ENVIRONMENTAL QUALITY OFFICE OF AIR QUALITY AND RADIATION PROTECTION RADIATION PROTECTION DIVISIoM l
BATON ROUGE, LOUISIANA 70004-2135 i.it omt r.
t,tener twer e unwrnr em-rxrlP ATIOt1 DME D t, G Innnect lon 1 A-7050-LO1 I n i t-i n ]
Fobruary 28, 19'r SADf9fer%ff tlAA t w H ptA21*F*t AMivlTY*
ttAtJD SWPCE t tTFT i r it' At t tf t crW AIF Uvt1AINED eP ExposuPE t'Evit t l 4t* R9 987,
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i 4.
The licensee is authorized to receive, possess, and use sealed sources of Cobalt 60 and Iridium-192 where the radioactivity exceeds the amount of radioactivit specified in this licenso provided:
A.
Such not-
'es do not exceed the quantity speci fied per source by more than 10 f or Col u 60 or 20% for Iridium-192; B.
Records t.
the licensee show that no more than the maximum amount c radioactivity spocified per source above was ordered from the supplier _e transferor of the radioactive material; and C.
Levels of radiation for radiographic exposure devices and storage containel do not oxcend those specified in Section 540 of the Louisiana Radictie Regulations.
5.
The. licensee is authorized to receive, possess and transfer depleted uranium fo use as shielding material in amounts not greater than 999 kilograms.
6.
A.
Tests for leakaue and/or contamination of sealed sources listed in th schedulo shal1 be performed in accordance with Section 544 of the Louisian Radiation Regulations.
B.
Leak test samples may be taken using approved leak test kits and procedure specified in the Licensee's application.
7 Except as specifically provided otherwise by the license, the licensee shal possess and use radioactive material described in all schedules of this licens in accordance with statements, representations and procedures contained in th licensee's application dated January 29, 1993 and in all subsequen correspondence.
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Gustave Von Bodungen, P.E. parc race or rAars Assistant Secretary February 8, 1993 3
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