ML20202C570
| ML20202C570 | |
| Person / Time | |
|---|---|
| Site: | 07100440 |
| Issue date: | 06/23/1986 |
| From: | Andresky E, Drake K PROFESSIONAL SERVICE INDUSTRIES, INC. (FORMERLY PTL-I |
| To: | |
| Shared Package | |
| ML20202C505 | List: |
| References | |
| IR-NG-QA-1, NUDOCS 8607110314 | |
| Download: ML20202C570 (10) | |
Text
.
@m %h PTL-INSPECTORATE INC.
PTL-INSPECTORATE, INC.
850 Poplar Street Pittsburgh, PA 15220 PROCEDURE:
Quality Assurance Program for Radioactive Material Packages (10 CFR Part 71 QA Program)
PROCEDURE NO:
IR-NG-QA-1 ISSUE DATE:
June 23,1986 Prepared By:
E.L. Andresky
/
Radiological Safety Coordinator Accepted By:
K.D. 'Dra%
Radiation Safety Liaison Officer 8607110314 860623 PDR ADOCK 07100440 C
PDR Page 1
of 4 Pages
PTL-INSPECTORATE INC.
Y Procedure No. IR-NG-QA-1 Date: June 23,1986
- 1. Organization The final responsibility for the Quality Assurance (QA) Program for Part 71 requirements rests with PTL-Inspectorate, Inc. Design and Fabrication shall be conducted under this QA Program by radioactive material suppliers. The QA Program is implemented using the organizational chart shown in Appendix A.
The Liaison Officer is responsible for overall administration of the prohram, training and certification, document control, and auditing.
The Liaison Officer and Radiological Safety Coordinator are responsible for the handling, storing, shipping, inspection, test and operating status and record keeping. All persons listed under Liaison Officer as shown in Appendix A are responsible.
- 2. Quality Assurance Program The management of PTL-Inspectorate, Inc., established and implements this QA Program.
Training, prior to engagement, for all QA funcations is required acccrding to written procedures. QA Program revisions will be made according to written procedures with management approval. The QA Program will ensure that all defined QC procedures, engineering procedures, and specific provisions of the package design approval are satisfied. The QA program will empha' size control of the characteristics of the package which are critical to safety.
The Radiological Safety Coordinator shall assure that all radioactive material shipping packages are designed and manufactured under a QA Program approved by the Nuclear Regulatory Commission for all packages designed or fabricated after January 1,1979.
This requirement will be satisfied by receiving a certification to this effect from the manufacturer.
- 3. Document Control All 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 Liaison Officer.
The Radiological Safety Coordinator shall insure that all QA functions are conducted in accordance with the latest applicable changes to these documents and 10 CFR 71.
- 4. Handling, Storage and Shipping Written safety procedures concerning the handling, storage, and snipping of packages for certain special form radioactive material will be followed. Shipments will not be made unless all tests, certificatins, acceptances, and final inspections have been completed.
Work instructions will be provided for handling, storage, and shipping operations.
Radiography and Nuclear Density Operators shall perform the critical handling, storage, and shipping operations.
Page 2 of 4 Pages
PTL-INSPECTORATE INC.
h Procedure NO. IR-ND-QA-1 Date: June 23,1986 5.
Inspection, Test, 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 of packages will be positively maintained by written procedures.
Radiography and Nuclear Density Operators shall perform the regulatory required inspections and labeling in accordance with written procedures. The Radiological Safety Coordinator shall ensure that these functions are performed.
6.
Quality Assurance Records Records of package approvals, procurement, inspections, tests, operating logs, audit results, personnel training and qualifications and records of shipments will be maintained.
These records will be maintained in accordance with written procedures. The records will be identified and retrievable. A list of these records, with their storage locations, will be maintained by the Radiological Safety Coordinator.
7.
Audits Established schedules of audits of the QA Program will be performed by Regional VP, Radiological Safety Coordinator, or Assistant Radiological Safety Coordinator. 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. Each activity will be audited at least once per year. Audit reports, will be maintained as part of the quality assurance records.
Members of the audit team shall be responsible in the activity being audited.
8.
Document Certifications Document certification is part of this program and are attached as Appendixes:
Appendix A - Organizational Chart Appendix B - IAEA Certificate of Competent Authority Certificate No. USA /0095/S (Rev. 5) (Source Production and Equipment Co.)
Appendix C - IAEA Certificate of Competent Authority Certificate No. USA /0166/S (Rev. 4) (Gamma Industries, Inc.)
Appendix D - Competent Authority Certification Certification No. USA /6717/B (U)
(Gamma Industries, Inc.)
Appendix E - QA Program Approval, Docket No. 71-0010 (Gamma Industries, Inc., expires 2/28/90)
Appendix F - Certificate of Compliance - USA /6717/B (U)
(Gamma industries, Inc., expires (7/31/90)
Page 3 of 4 Pages
@Ih PTL-INSPECTORATE INC.
Procedure No. IR-ND-QA-1 Date: June 23,1986 8.
Document Certification - Cont'd Appendix G - Certificate of Compliance - USA /9135/B(U)
Gamma Industries, Inc., expires 4/30/87)
Appendix H - Certificate of Compliance - USA /9126/B(U)
(Gamma Industries, Inc., expires 10/31/8 8)
Appendix 1
- Certificate of Compliance - USA /9127/B(U)
(Gamma Industries, Inc., expires 10/31/88)
Appendix 3 - Certificate of Compliance - USA /9128/B(U)
(Gamma Industries, Inc., expires 10/31/8 8)
Appendix K - QA Program Approval, Docket No. 71-0102 (Source Production & Equipment Co., Inc., expires 3/31/91)
Appendix L - Certificate of Compliance - USA /9036/B(U)
(Source Production & Equipment Co., Inc., expires 10/31/9 0)
Appendix M - Certificate of Compliance - USA /9056/B(U)
Source Production & Equipment Co., Inc., expires 3/31/91)
Appendix N - Competant Authority Certification Certification No. USA /9160/B(U)
(Rev. O) (Gulf Nuclear, Inc., Docket No. 71-9160)
Appendix 0 - Certificate of Compliance - USA /9160/B(U)
(Gulf Nuclear, Inc., expires 4/30/89)
Appendix P - Type A Certfication (Troxler Electronics Laboratories, Inc., (Letter)
Appendix Q - Campbell Pacific, Inc., Special Form and Packaging (IAEA Certificate of Competent Authority No. USA /Oll5/S.
Page 4 of 4 Pages
@lh PTL-INSPECTORATE INC.
ORGANIZATIONAL CHART r
3 K.D. Drake Executive Vice President &
Liaison Officer J'
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l E.L. Andresky J.E. Nalepa Radiological Safety Assistant Radiological Coordinator Safety Coordinator A
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I Radiation Safety Officer Assistant Radiation Safety (District Office)
Officer (District Office)
J J
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r Radiograpner er Nucler.r Gauge Operator 2
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3 Assistant Radiographer J
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amm mammmmmmanummmmmmmme musemummmmmmmmuseum m APPENDIX -A-
A (15 Department 400 Seventh Si. S w Of Dansportation washington. D C 20590 Research and specioIPrograms IAEA CERTIFICATE OF COMPETENT AUTHORITY Administretton Special Form Radioactive Materials Encapsulatie r3 Certificate Number USA /0095/S (Revision 5)
This certifies that the encapsulated sources, as described, when loaded with the authorized: radioactive contents, have been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in IAEA 1/ and USA 2/ regulations for the transport of radioactive materials.
I.
Source Oescription - The sources described by this certificate are identified as Source Production and Equipment Co. Models G-1, 3, 23, 36, 37, 38, 39, 40; T-1, 2, 5, 6; B-2, 8,10,16; and R-3,6 and 9, which are encapsulations constructed of stainless steel with welded closures and measure 1/4" in diameter by approximately 3/4" long.
Construction is in accordance with Source Production and Equipment Co. drawing number 101 dated 8/14/85.
11.
Radioactive Contents - The authorized radioactive contents of this source consist of not more than 110 curies of cobalt-60 or 240 curies of iridium-192 as metal pellets.
111.
This certificate, unless renewed, expires November 30,1990.
This certificate is issued in accordance with paragraph 803 of the IAEA Regulations 1, and in response to the October 31, 1985, petition by the Source Production and Equipment Co., Inc., Kenner, Loulslana, and in consideration of the associated information herein.
Certified by:
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Richard R. Rawl (O'hte) l Chief, Radioactive Materials Branch l
Office of Hazardous Materials Transportation 1/ " Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Edition", published by the International Atomic Energy Agency (IAEA), Vienna, Austria.
~
2_/ Title 49, Code of Federal Regulations, Part 170-178, USA.
i Revision 4 - extended expiration date.
Revir. ion 5 - added 7 model designations and drawing reference; increased allowed contents; extended expiration date.
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UC IK' Of ironsportafon Research and IAEA CERTIFICATE OF COMPETENT AUTHORITY 5pecio! Programs Mministraten Spec al Form Radioactive Material Encapsulation Certificate Number USA /0166/5 (Revision 4)
This certifies that the encapsulated sources, as described, when loaded with the authorized radioactive contents, have been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in IAEA 1/ and USA 2/ regulations for the transport of radioactive materials.
1.
Source Description - The sources described by this certificate are identified as the following Gamma Industries models which are constructed according to the listed drawing numbers:
Model No.
Drawing No.
VD and VD(HP) 602-7001-004 NB, NBG and NB(HP) 602-7001-005 Single Encapsulation Universal Source 602-7001-006 Double Encapsulation Universal Source 602-7001-007 Single Encapsulation Side Weld 602-7001-008 All models are welded encapsulations constructed of 300 series stainless steel or ARMCO Type 17-4PH stainless steel.
11.
Radioactive Contents - The authorized radioactive contents of these sources consist of not more than:
Model No.
Contents VD and VD(HP) 300 curies of:
Barium-131 Manganese-54 Cadmium-109 Phosphorus-32 Calcium-45 Rubidium-86 Calcium-47 Selenium-75 Cesium-137 Strontium-85 Chlorine-36 Thallium-204 Chromium-51 Thulium-170 Iridium-192 Tin-ll3 Cobalt-60 Ytterbium-169 Iron-59 Zinc-65 l
l M- -Ek APPENDIX -C-l
r Certificate Number USA /0166/S, Revision 4 11.
Radioactive Contents (continued)
Model No. (cont'd)
Contents (cont'd)
NB, NBC and NB(HP) 25 Curies Americium-241 30 millicuries Ra-226 i
500 millicuries Americum-241 and Cesium-137 mixture Single Encapsulation Universal Soruce 500 curies Iridium-192 20 curies Cobalt-60 Double Encapsulation Universal Source 3000 curies Iridium-192 2000 curies Cobalt-60 Single Encapsulation Side Weld 300 curies Iridium-192 20 curies Cobalt-60 111.
This certificate, unless renewed, expires July 30, 1987.
4 This certificate is issued in accordance with paragraph 803 of the IAEA Regulations and in response to the May 14, 1984 petition by Gamma Industries, Baton Rouge, Louisiana, and in consideration of the associated information therein.
Certified by:
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Richard R. Rawl (Ipte) U Chief, Radioactive Materials Branch Office of Hazardous Materials Regulation Materials Transportation Bureau 1/ "Saf ety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition", published by the International Atomic Energy Agency (IAEA),
Vienna, Austria.
2/ Title 49, Code of Federal Regulations, Part 170-178, US A.
Revision 4 issued to correct materials of construction specification.
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US Deportrnent 400 seventn si s w Of TronSportofon Washington D C 2M90 Research and Special Picyseis Administration COMPETENT AUTHORITY CERTIFICATION FOR A TYPE B(U)
RADIOACTIVE MATERIALS PACKAGE DESIGN CERTIFICATE USA /6717/B(U), REVISION 2 This certifies that the radioactive materials package design described below has been certified by the competent authority of the United States as meeting the regulatory requirements for q Type p(re)gulations.
U packaging for radioactive materials as prescribed in the IAEA and USA
- 1. Package Identification - Model No.6717-B.
- 2. Packaging Description and Authorized Radioactive Contents as described in Nuclear Regulatory Commission Certificate of Compliance No. 6717, Revision 6 (sttached).
- 3. GENERAL CONDITIONS -
- a. Each user of this certificate must have in his possession a copy of this certificate and all documents necessary to properly prepare the package for transportation.
- b. Each user of this certi fic ate, other than the original petitioner, shall register his identity in writing to the Office of Hazardous Materials Regulation, Research and Special Programs Administration, U.S.
Department of Transportation, Washington D.C. 20590.
- c. This certificate d6es not relieve any consignor or carrier from comoliance with any requirement of the Government of any country through or into which the package is to be transported.
I" Safety Series No. 6 Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition ( As Amended)" published by the International Atomic Energy Agency (IAEA), Vienna, Austria.
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APPENDIX -D-
- I
- CERTIFICATE USA /6717/B(U), REVISION 2
- 4. The package shall bear the marking USA /6717/B(U) in addition to other required markings and labeling.
- 5. This certificate, unless renewed, expires on July 31, 1990.
Certified by:
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August 6, 1985 Richard R. Rawl Chief, Radioactive Materials Branch Office of Hazardous Materials Regulation Materials Transportation Bureau Revision 2 - issued to incorporate NRC certificate 6717, Revision 6; extend expiration date.
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_ _...........,,,,,,,g u.s. NUCLEAR REOUL, _ AY CorMIS$10N 1.APM:0 VMBEA QUALITV ASSURANCE PROGRAM APPROVAL
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FOR RADIOACTIVE MATERIAL PACKA2ES WSIO
]BER 1;
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j; Pursuant to the Atomic Energy Act of 1954.as amended, the Energy Reorganization Act of 1974. as amended, and Tit!e 10. Code of Federat
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Regulations. Chapter 1. Part 71, and in reliance on statements and representations heretofore made in item 5 Dy the person named an item 1
- l
- 2. the Ouality Assurance Program identified in item 5 is hereby approved This approvalis issued to satisfy the requirements of Section l'
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71101 of 10 CFR Part 71. This approval is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission
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y now or hereafter in effect and to any conditions specified below.
2 l[
1l2NAME
'l 3 EXPIRATION DATE I
f Gama Industries February 28, 1990
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STACE' ACORESS 4
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Baton Rouge
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"%E2 71-0010
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k 5 cuAuTv assurance PROGRAM APPLICATION DATEtS)
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January 30, 1985 1
i 6 CONOITIONS 1
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.i 2!
A.
Activities Conducted under applicable criteria of Subpart H of 1
10 CFR Part 71 to be executed with regard to transportation packages.
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B.
This approval is limited to sealed sources.
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'j Charles E. MacDona d FEB II E 1 CHIEF TRANSPORTATION CERTIFICATION BRANCH l; DIVISION OF FUEL CYCLE AND MATERIAL SAFETY APPENDIX -E-ll OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS F
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CERTIFICATE OF COMPLIANCE I
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USA /6717/B(U) 8 8 E A v9.E k
a ' s certAcate s ssuec to ce t tv inat tme cacsageg anc cor rents cescr ceo 'n etera 5 ce.ow meets tae ace.cacie safety stancarcs ser for m in T tre c cace i
ej or :ece<a* 2e;.at>c s Dart ' Dac a;>ng Of Aacroa:n.e Yater ais for 'ransco t arc Transcortation o' namoact.ve Materiat Uncer Certa.n Cormt ons
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'IT'.E ANO 'CENTIFICATiCN 08 Af
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Ganma Industries Nuclear Packaging, Inc. application dated P.O. Box 2543 June 20, 1975, as supplemented i
i Baton Rouge, LA 70821 i
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i COCKET NuuBER 71-6717 l:
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'*.s Cert.? Cate 's Conc:tional woon f distia; the re ' orernents Cf 10 CF A part 71 as acDisCADie anc tae Conditions sCecified Demw e
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s (a)
Packaging i
i I
(1) Model No.:
6717-B I
(2)
Description l
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Radiographic device within a protective overpack.
The overpack consists of an outer container which is a 10-gallon open head steel drum having a minimum 20-gauge body and cover, welded seams and a clamp-ring type f
head closure.
The void space between the inner and outer container is N
filled with 1-1/2" thick molded asbestos free liner on sides, top and k
bottom, plus molded polyurethane filler to position and secure the radiographic device within the drum.
Maximum gross weight of the 9
package not to exceed 75 pounds.
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(3)
Drawing 94 The packaging is constructed in accordance with Nuclear Packaging Inc.
4 Drawing No. SK-D-1, Rev. 2.
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APPENDIX -F-
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.s Page 2 - Certificate No. 6717 - Revision No. 6 - Docket No. 71-6717 5
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I (b) Contents
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E (1) Type and fann of material E
F Iridium 192 as sealed sources which meet the requirements of special l
g f ann radioactive material.
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4 Et 4
(2) f4aximum quantity of material per package g
g F
l 200 curies.
F h
6.
The contents must be secured in a single snug-fitting inner radiographic device
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which has a metal outer wall and meets the requirements of DOT Specification 7A g
packaging.
F F
4 7.
The source shall be secured in the shielded position of the radiographic device f
3 by the shipping plug, source assembly, and locking device.
The shipping plug
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j and source assembly used must be fabricated of materials capable of resisting a s
i n
1475*F fire environment for one-half hour and maintaining their positioning i
3 function.
The ball stop q,f the source assenbly must engage the locking device.
E 5
The flexible cable of the source assembly and shipping plug must be of sufficient l
length and diameter to provide positive positioning of the source in the shielded e
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position.
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g 8.
The packaging authorized by this certificate is hereby approved for use under 3
the general license provisions of 10 CFR971.12.
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f 9.
Expiration date:
July 31,1990.
I E
1 E
d 5
REFERENCES i
E Nuclear Packaging, Inc. application dated June 20, 1975.
E N
e Supplements dated:
August 8,1975; and February 26, 1980.
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION g
E E
Charles E. MacDonald, Chief g
Transporation Certification Branch E
Division of Fuel Cycle and k
fiaterial Safety, NiiSS E
E Date:
JUL 2 21985 l
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CERTIFICATE OF COMPLIANCE I, '0 C'" "
FOR RADIOACTIVE MATERIALS PACKAGES lI
- i. cEne,s.cATE % usta o aEvision Nuusta c PACKAGE iCENTIFiCArioN NupBEa a PAGE hvW8Ea
. rotAL NvMBEa PAGES 9135 1
USA /9135/B(U) 1 2'
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. Tn.s cen.t.c.i..s,ss.o to cenie, inat ie. pac =.a.ag na contents aescr.o.a.n n m s e.io. me.is in.appi.c.oi.
e.iv stana.ra
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31 of Feae a! Regsat.ons pari ?,
P.cmaging of Aaaeoactive Maier.ais for Tr.nsport.no Tr.nsportation of Raaio.c0ve Mat.nal Una.r C.rt.in Canadions g
o Tn. cen,r,cm aoes noi r..... ene cons.gnor erom compi.ax
..in angeov.r m.nr of in. r goiai ons or in, u s o.a.nment or Tr.nsponanon or oiner E
Appi case r as.. tory.a.nc... ncioa.n; in, ao..,nm.ni o,.ny coenir, in,oogn o, inio on.cn in. pac..g...n o. ir.n.pon.a E
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2 v.,,s cE,are.c Art is issuto oN r-E eAS15 oF A SAstry ANALT$l$ aEPont oF TME PACm AGE DESIGN OR APPUCArioN E
. paE Aaec er,N.m..w,a e...,
o tirtE ANo ioENTiricArios or aEpoar on AppticArios E
Gamma Industries Gama Industries application dated
'E P.O. Box 2543 March *4, 1982.
E Baton Rouge, LA 70821
?
18 3f 71-9135 e oocnErNuAaEn A
. ccNo,s.c.Ns g
Tr.s c.n..cn. conaa.ona, upon voit,n.ng in. r.au,,.m.nis on to cra p.rt 7i....ppi e.on...na in. cona.i.on.
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s if (a)
Pac kaging E
d (1) Model Nos.:
Century 5, Century SA, Century Universal S, and l
i
!i Century Universal SA j
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(2) Description i
jt I
I E
J A steel encased, uranium shielded radiographic device. The shipping j
container is approximately 7.0 inches long and 5.5 inches in diameter.
lE The radioactive source assembly is housed in a Zircalloy or titanium j
Pl "S " tu be. The tube is surrounded by depleted uranium metal as shielding
!g ma terial. The depleted uranium shield assembly is encased in a steel 6
1
'g p
housing. The void space between the depleted uranium shield assembly I
pi and the outer container is filled with a polyurethane foam. The d
packages differ from one another only in the construction and locations lI
~
l of the lock boxes (two types of lock boxes). The gross weight of the
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packages is 45 pounds.
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(3) Drawings II d
The packagings are constructed in accordance with Gamma Industries l
18 Drawing Nos. 821-1001-439A, Rev. - (Century S&SA); and 821-1001-441A, Rev. - (Century Universal S&SA).
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conomous toontonuea; ll il Page 2 - Certificate No. 9135 - Revision No.1 - Docket No. 71-9135
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(b) Contents r
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(1) Type and form of material
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l Iridium 192 as sealed sources that meet the requirements of special f
i
(
fom radioactive material.
- f
,r (2) Maximum quantity of material per pa.;kage f
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x 120 curies i
r
- 6.
The lock box assembly must be attached to the package (can) with twelve (12),
I 5/16"-18UNC x 1/2" long, ASTM 18-8, 304 stainless steel bolts. The minimimum
{
depleted uranium shielding thickness must be 1-9/16. inches.
I L
l 7.
The source must be secured in the shielded po.iitton of the packaging by the I
safety cap, source assembly and lock box assembly. The components used to r
secure the source must be fabricated of matrials capable of resisting a 1,475'F I
i$
fire envirorment for one-half hour and maintaining their positioning function.
lli
[g The ball stcp of the source assembly must engage the locking device. The flexible t
cable of thr. source assembly must be of sufficient lehgth and. diameter to provide t
lg positive positioning of the source at the optimum shielding position at the l
lP center of the "S" tube.
I I
- 8.
The name plates must be fabricated of materials capable of resisting the fire l
test of 10 CFR Part 71 and mintaining its legibility.
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9.
The package authorized by this certtficate is.hereby approved for use under the i
general license provisions of la CFR 671.12 I
10.
Expiration date: April'30, 1987.
l REFERENCE t
l l
l Gamma Industries application dated March 4 1982.
j FOR THE U. S. NUCLEAR REGULATORY COMMISSION l
I k0A i
Cha les E. MacDonald, Chief l
Transportation Certification Branch i
Division of Fuel Cycle and I
Material Safety, PetSS I
S P 0 61983 Date:
I I
I i
I l
I I__________________________--__-------------===I
4,, m uhu aravd:"EP1*3*Kiciliikm2c':2t1s:'newamuracannusc';arntwetene ngw~,wwr N
AR R COMMISSION i'
CERTIFICATE OF COMPLIANC
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FOR RADICACTIVE MATERIALS PACKAGES f
s a CEm'er'CA'E N.vEEm t RE VISION NUMBEE c P ACK AGE iCENTs8 sC AT ON NUMBER o PAGE NUMBEn
, TOT AL NuwSEA P AGEE ii 9126 3
USA /9126/B(U) 1 2
j ; 2 pee Ave E 1
a Tn.s certifica'e s sssec to cert ', inat the pacmag>ng anc contents describec in item 5 beso* meets tne appocass safety stancarcs set forta in Title 10 Code e
{;
o 8ecerar Aegsa ens Part 71 Pac =agmg of Aasicactive Materiais for Transport anc Transportation of Aacioactive Material Uncer Ce ta.a Conc tions s
[
e Tn s certAca e coes not re'ie.e tne consignor ' rom comphance witn any reasirement of the regaistions of the U S Department of Transportation or otner appocae e regsatory agent es inciacing tne government of any country througn or into whicn the pacmage ein be transportec r
E J 'ssis CE A'is.C ATE iS '55.EC CN Taf 645 5 OF A SA5ET* ANA YS S AEpont Os THE P ACK AGE DE56CN OR AppuCATiON a paf p AAE0 8' 'Name s9c a23ress, e TITLE ANO iCENTiFiCATiON Or mEpORT On AppucATION g*
Gamma Industries Gama Industries application y}
P.O. Box 2543 dated May 20, 1978, as supplemented.
i Baton Rouge, LA 70821 1
71-9126 c OOcxET Nuvef.
3. cese T,cNs Tms ce t:f.cate is cone.tiona' w::a uinng tne recuremeats of 10 CFA Part 71. as apphcaD e and the concitions sDeci6ec be>ow
['
(a)
Packagi ng
-i (1)
Model Nos.:
20, 20A, 50 and 50A i
j (2)
Description j
A steel encased, uranium shielded radiographic device.
The shipping y
container is approximately-21 inches long, 23 inches wide and 42 inches high.
The radioactive source assembly is housed in a Zircalloy i
or titanium "S" tube.
The tube is surrounded by depleted uranium t
metal as shielding material.
The depleted uraniun shield assembly is i
encased in a steel housing.
The void space between the depleted uranium shield assembly and the outer container is filled with a q
polyurethane foam.
The gross weight of the container is 325 pounds.
1 (3)
Drawings
}
The packaging is constructed in accordance with Ga raa Industries Drawing Nos. 821-1001-128, Rev. 4; 821-1001-129, Rev.1; and 180-01, Rev. 1.
(b)
Contents (1)
Type and form of material Cobalt 60 as sealed sources that meet the requirements for ecial form radioactive material.
n 5
e s
APPENDIX -H-(fQfA1 A /' 7p l
- )fV U Lp r '
....--------------------mem -s -
l
.r
......__Z_.Amm._________________________________a conom::ns icontinucas J
l l
Page 2 - Certificate No. 9126 - Revision No. 3 - Docket No. 71-9126 1
(b)
(2) Maximum quantity of material per package j
i Model No.
Quantity j
20 and 20A 20 curies 50 and 50A 50 curies 6.
The source shall be secured in the shielded position of the packaging by the safety plug assembly, source assembly and lockbox assembly.
The components used to secure the source rust be fabricated of materials capable of resisting a 1475'F fire environnent for one-half hour and maintaining their positioning I'I function.
The ball stop of the source assembly must engage the locking device.
The flexible cable of the source assembly and safety plug assembly must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.
7.
The can and side plates must be a minimum of 1/4-inch thick carbon steel. The can and side plates shall be joined by full penetration welds.
All other welds shall be fillet welds having sufficient throat thickness to develop strength equal to or greater than the metals being joined.
8.
The nameplates shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12.
10.
Expiration date:
October 31, 1988.
REFERENCES Gamna Industries application dated flay 20, 1978.
Supplement dated:
October 25, 1978.
I FOR THE U.S. NUCLEAR REGULATORY COMt11SSION l
I MCharles E. Ma onald, Chief 1.
j, j
Transportation Certification Branch Division of Fuel Cycle and Material Safety, NftSS i
I I'
I l
Date:
W 06 7383 I.
I I
l' b - - -
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~..
r-ww.swey m p gs_. b
. -,_ m a r a=s u.i r r a a=A + i a e.e a r m.
{
J.S. NUCLEAR REGULATO~iY CoMZISSION N CFfWJ618 CERTIFICATE OF COMPLIANCE 4n c C"' '
FOR RADIOACTIVE MATERIALS PACKAEES k-D #EviSiON NVVBE A C PACM AGE iCENTiFiCatiON NUMBER o PAGE NUMBER e TOT A. NVMSEm PAGE 5 g
- a Cents C A'E NeUBES 9127 3
USA /9127/B(U) 1 2
g
$ 2 paE Ave *E a inis cc ti icate is isswe3 to cert f y taat tne cacna; ng anc conte 9ts cescribec in item $ below meets the appl cabie safet y stancarcs set fortn in Tit:e 10 Coce i
f g
of 8eceral Aeg.s anoas Part 71 Pacnag.ng of Aasicactive Materiais for Transcort and Transoortation of Aadioactive Material Uncer Certain Concitsons i
Tnis cert ficate coes not refie.e tne cons.gaor from comonance witm any reasirement of the regstatiors of tne U S Decartment of Transportation or otner b
applicabie regstatory agencies inctuo.ng the government of any cowntry throwgn or into which tme pacnage **ll be transportec 4
3
'd 3 Tris CERT FsCATE iS ISSwfC ON TwE BASIS OF A SAFETv ANALiSiS REPORT OF TME PACnAGE CESiGN OA APSLIC A TION e TITLE ANC ICENTIFiCATiON OF RE*0AT OA APPLICATION 3
a PRE 8A AED Sv <hame saa Aao-ess-3 Ganma Industries Ganna Industries application dated May 20, 1978, y
4 P.O. Box 2543 as supplenented.
O Baton Rouge, LA 70821 Q
s 71-9127 5
e OOC Et NuusEA a CCN; MONS 1
Tn.s certificate is conc ticna: upon tumtheg tne recwirements cf 10 CF A Part 71. as appucacie and the conditions specif.ec beto*
9as
- q (a)
Packaging
.i i
(1) Model Nos.:
100, 100A, 200 and 200A 4
4;j (2)
Description i
A steel encased, uranium shielded radiographic device.
The shipping 3
containers is approximate 1f 21 inches long, 23 inches wide and 42 inches high.
The radioactive source assembly is housed in a Zircalloy or titanium "S" tube.
The tube is surrounded by depleted uranium metal as shielding material.
The depleted uranium shield assembly is encased in a steel housing.
The void space between the depleted
- j uranium shield assembly and the outer container is filled with a i
i polyurethane foam.
The gross weight of the container is 500 pounds.
1 8
(3)
Drawings il The packaging is constructed in accordance with Gamma Industries i
Drawing Nos. 821-1001-128, Rev. 4; 821-1001-129, Rev.1; and 180-01, l
Rev. 1.
i (b) Contents i
4 (1)
Type and fonn of material g
i Cobalt 60 as sealed sources that meet the requirements of special form i
4 radioactive material.
i g
Oj,, o j
t
' c.,;
L_. 4 4 g A[/R f
APPENDIX -I-
~
E y a, mv
p.y TraAm A.:2. am ammm m mm m.= = m.=. mm - m a a a mm a - - - a mm - - -ma m - - - -
.a m.g,m,mf.m; 3
(
CONolTloNS icontonuse) 3 aj Page 2 - Certificate No. 9127 - Revision No. 3 - Docket No. 71-9127 3
3
.I 1
(2) Maximum quantity of material per package I
Model No.
Quantity j
l 100 and 100A 100 curies y
200 and 200A 200 curies 1
6.
The source shall be secured in the shielded position of the packaging by the 3
safety plug assembly, source assembly and lockbox assembly.
The components used
.j to secure the source must be fabricated of materials capable of resisting a 1475*F fire environment for one-half hour and maintaining their positioning a
3 function.
The ball stop of the source assembly must engage the locking device.
1 The flexible cable of the source assembly and safety plug assembly must be of i
sufficient length and diameter to provide positive positioning of the source in j
the shielded position.
lI 7.
The can and side plates must be a minimun of 1/4-inch thick carbon steel.
The q
y can and side plates shall be joined by full penetration welds.
All other welds a
shall be fillet welds having sufficient throat thickness to develop strength 3
equal to or greater than the metals being joined.
1 8.
The nameplates shall be fabricated of materials capable of resisting the fire j
test of 10 CFR Part 71 and maintaining their legibility.
y 1
1 9.
The package authorized by this certificate is hereby approved for use under the I
general license provisions of 10 CFR 971.12.
l 10.
Expiration date:
October 31, 1988.
1 1
1 REFERENCES 1
l Ganna Industries application dated May 20, 1978.
l Supplement dated:
October 25, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMiilSSION 1
l Charles E. liacbonald, Chief g
Transportation Certification Branch I
Division of Fuel Cycle and I
liaterial Safety, NMSS I
I, l'
Date:
007 0 6 m)
(
t S
e.
' Aim diii m'1NE-$'*nBSE*3E"h4Nmwmnnu a a a A m -;-cab ri mtag*
N R
Rm ssioN CERTIFICATE OF COMPLIANCE I~N'""
FOR RADIOACTIVE MATERIALS PACKAGES
',0 C '" "
C P ACMAGE #DENTIFICATION NUMBER O PAGE NUMBER e TOTAL NuuBEA FAGES o AEvi,40N NUMBE A 9128 3
USA /9128/B(U) 1 2
g a CEntifiCATE NUMBEm
[Ell a Tnis certif.Cate is.ssvec to Certif y inat t"e caCaag ng and contents described it ttem 5 below meets tne apphcabl PM&M96E Packag.ng of Racioactive Materials for Traasport and Transportation of Radioactive Material Under Certain l
cf FederalMegsiabons Part 71 Tn's Cert'Ocate coes not ret eve the cons gnor f rom Compuance with any requirement of the regafahons of the U S Departmen l
aCchCable regsiatory agencies.ncluc.ng tne government of any Country through or into wnich tne paChage will be transported b
il
- 0.,,_.s m.7,.icATEls,ss _,-E....s e..,A.E,..N.. sis.E.e.,e., E.Ac.Ao m s _. A..<, CAT.
T ATLE AND IDENTIFICATION OF REPOpt OR APritCATION t
Gamma Industries application dated May 20, 1978, ll a FAEP AmED BV 'Name a ic Awess' Gamma Industries P.O. Box 2543 as supplemented.
4l Baton Rouge, LA 70821 I
M 71-9128 C oocar NuueEa sj Tnis Ce*t?iCate 's COncitiO9a' wC0" 'uththng tne reQuarements of 10 CFR Part 71 as apphCaDie and the Cond.t.095 $Decified beio*
e CCCTiON, M 5 y
(a)
Packaging b
i (1) Model No.:
C-8 A steel encased, uranium shielded source exchanger.
The shipping container is approximately 16 inches in diameter,13 inches long and E
The radioactive 26 inches high in its skid mounted configuration.
A source assembly is housed in a Zircaloy or titanium "S" tube.
septum at the center of the "S" tube prevents moving the source assembly 4
beyond the optimum shielding position. The tube is surrounded by h
depleted uranium metal as shielding material.
The depleted uranium shield assembly is encased in a steel housing.
The void space between the depleted uranium shield assembly and the outer container is filled The gross weight of the container is 500 gi with a polyurethane foam.
Niti pounds.
4 l
(3)
Drawings The packaging is constructed in accordance with Gama Industries i
821-1001-033, 191, 821-1001-347, 821-1001-389, 821-1001-i Drawing Nos.
116, 821-1001-414, 811-1001-346, 811-1001-408, 801-1001-336, 801-1001-d 4
l 328, 801-1001-283, 801-1001-338, 801-1001-224 and 801-1001-159.
i
's.
i y
i.
A 6
f f
4*s Ns, l
s 9
II I
N I
I I
mIII - - m VL lh' \\h l'
APPENDIX -J-I j,
9 m vi w g p ).
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- - -._ nurwmm mygam]v w w m m m w w.M
.aswr Q wrw i
(
ccnomcus tecnonous n
p I
71-9128 lp Page 2 - Certificate No. 9128 - Revision No. 3 - Docket No.
!E I
E 4
lj I
M 5.
(b) Contents
{i (1) Type and forn of material i
N Cobalt 60 as sealed sources that meet the requirements of special form radioactive material.
g (2) Maximum quantity of materisi per package I-200 curies The source shall be secured in the shielded position of the packaging by the T
The components used to secure 6.
safety cap, source assembly and lockbox assembly.the source n The environment for one-half hour and maintaining their positioning function.
The flexible ball stop of the source assembly must engage the locking d positive positioning of the source at the septum in the shielded position.
The The can and side plates rust be a minimum of 1/4-inch thick carbon steel.
All other welds can and side plates shall be joined by full penetration weld 7.
equal to or greater than the metals being joined.
The nameplates shall be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining their legibility.
8.
The package authorized by this certificate is hereby approved for use und 9.
general license provisions of 10 CFR 971.12.
10.
Expiration date:
October 31, 1988.
REFERENCES Gamna Industries application dated May 20, 1978.
y I
I Supplement dated:
October 25, 1978.
FOR THE U.S. NUCLEAR REGULATORY COMMI I
I I'
f.
WE p Charles E. Ma{ Donald, Chief Transportation Certification Branch I
I.
I' Division of Fuel Cycle and l'
tiaterial Safety, NMSS l'
OCT 0 61953 Date:
i 1:
1 1
s' i
Il
...,__--_-______,________m-----or
p.1;rgc.C; ;n.:.Tc~;w;a..e. :2:,h;*d;t.~1N;;2; 5:.c:a;;* c:1.T;;;.::;L%:2?1*3*1?271. a 1h:?2?L L'U,7&hE?1?n{l=f3*3?;?;,*s ;
I Ai'l Hov At t UMiu u
-[
d U.S. NUCLEAR REGULATORY COMMISSION l
,c.c con u s" 0102
-I OUALITY ASSURANCE PROGRAM APPROVAL t -
FOR RADIOACTIVE MATERIAL PACKAGES REwsiosp mn i;
i.-m 4_
[
s<_
i Pursuae: te Pe Ato-c Energ, Act cf 1954.as amended.the Energy Recrgangation Act of 1974.as amenced.anc Titic 10. Code of Feceral
{
Peguate ns. C"apte-. Dart 7' and in rel ance on statements and representat.ons heretof ore mace in item S Dy the person named in item 1;
I
- 2. tne Cual.ty Ashrance Prcpam icentified in item 5 is hereby approved This approvalis issued to satisfy the requirements of Section
- I 71101 of 10 CFR Part 71 This appro.a! is subject to all app!icable rules. regaf ations.and orders of the Nuclear Regulatory Comn'ission I
g now or hereafter en ef!ce* anc to a"y cend.t.cns specified below f
- l d
11 3 E AP;AATioN DATE
- 9 2 NAMd k
Source Production & Equipnent Comoany, Inc.
j l March 31,1991
.i d
since accatss 625 0xlev Street i.: cec. tr r.uMet b
1 arv sr4TE inceoe
{71-010
l Kenner l
LA' 70062 l'
I g4 3 c.&.n aust....m
. w e u,. ca n,carcis, f
December E, 19~0, and February 6, 1986 q e x,o n:.s k
H i
IE kt'vi ties conducted under applicable criteria of Subpart H of 10 CFP fstj Part 71 :: be evecuted with regard to transportation packages for t:
+
la r2di r ut ve m te -ia' in S;ecial fo m.
i
- j.
- Wh E
!sa i
19
[4 e;i
.:li je 5
lie EE le le'i
!2 i.9 4
na f.5 I?
[C l[.
3 x1 I5 5
4, e
,4,j b Ao A f'lV7 /]/\\
(
Af Ujuan ur J.
i
[FOR THE U S. NUCLEAR REGULATORY COMMISSION 0
I f
b FEB 2 61986 Cher es t.
Ma c Donalti
$ CHIEF. TRANSPORT ATION CE ATIFICATION BA ANCH
- Division OF FUEL CYCLE AND MATERIAL SAFETY APPENDIX -K-q! OFFICE OF NUCLEAA P.'ATERI AL SAFETY AND S ACEGUAAD g
gg.g.,75g,
_mhuurm7x,r Tsummegmv3r
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(,
U.S. NUCLEAR CEGULATOY COMMISSION :
jNICFont61s CERTIFICATE OF COMPLIANCE ll4l
+sai
'o cra "
FOR RADIOACTIVE MATERIALS PACKASES i
- , a cExTis.cATE wueEa o af vision NuweEa e aACnAGE icENTIFICATION NuuSER e PAGE NuugEm e TOTAL NyusEn PAGE5 l
903G 5
USA /9036/B( )
1 2
g
'I a Tnis ce tificare es ss,.iec to cert.', inar tne pacna;,ng ano contents descrioso in item 5 below meets the applicacie safety stancaros set fortnin Title 10 Coce IIl i 2 peEius.E l
o' Fecerai Regwianons part ?1 pacnagieg o' Rao oactive Materiais for Transport ano Transportation of Asoicactive Material Uncer Certain Conestions
,gl t
Tm s co t.6cate coes not rene.e tne consignot ' rom compnance with any requirement of tne regulations of tne U S Department of T'ansportation or otner I}
j b
acci.cacie regsatory agencies enciwo.ng tne government of any cou try enrowgn or ento anien tne package wiu be transported Ej n
i
,g I
3 twis CERT 8 CATE 15 iS$vt: ON 'af S AS 5 C8 A SA8Eiv ANAuv5.S mEpcmT 0s TME 'ACK AGE CESIGN Cm AP*uCATiON I
O TIT E ANC iOENTiFICAfiON OF RE* CAT Om APPuCatioN I
a PEEpanED 87 dName aw daareas.
6 EI Source Production & Equipnent Co.
Source Production & Equipment Company 4tj l 625 0xley Street application dated January 23, 1975, as lIr l
Kenner, LA 70062 supplemented.
,I El E1i]
71-9036 g
s oce=Ev~uu.Ea Il l
-. CcNeiiie s
.Il Tnis certibcate.s comertionat woon tuffili>ng tne recuiremeats of 10 CFR Part 71 as acoucabie and tee conditions soecified beio.
t; (a)
Packagi ng l1 tl (1) Model No.:
C-1 gj Il (2) Description ll II A uraniun shielded radiographic source changer.
Configuration is y
< :l that of a rectangular box 9" high x 7.5" wide x 7" deep.
All
-
CERTIFICATE USA /9160/h(U), REVISION C
- k..Its p:kk6e shall tear ti.( r::arking USA /9160/E(U) in addition to other reycired merkincs and labeling.
- 5. Tr.i: certificate, ur.less renewed, expires on t.pril 30, 1989.
Curt r
March 13, 19C5 Eict.ard h. Ecwl Chief, Escioactive Materials Branch Office of flazardous Materials Regulation Matcrials Transportation Bureau Revision 0 - initial issuance.
'i
,.-..=,.:-..---
1 i L*1.L'L*
A CMMA.5 2 'A $ A
- "O WE p
.d U S NUCLE Aa CEGULAtoav COMMISSION -
- ;" T '"
CERTIFICATE OF COMPLIANCE l,
FOA R ADIOAcTivE MATERIALS PACK AGES
(
c,. ~
0 USU91 M;'c f.';
1 2
L.
.6
.e
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e
.. -. ;,.. n...... -.. :. c t -.
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..;.....,..;.....,.........-...,,.:.y,--.........,;..,._.
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- ....,.:..es
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)
Gulf Nuclear, Inc.
Gulf Nuclear, Inc. application dated
[
g 202 Medical Center Boulevard Janua ry 21, 1984, as supplemented, p.
P s
Webster, TX 77598
.I p
n m
,el kh 71-9160 g
c :c =t
- wet,
. ::s:., s T "s ce * '.ca'e 's ca:
- c a.,;0- v' n ; t*e e:v.e-e s c' 'C CFC par' it as aepheacie a c the oaca cas soe::f.ec be.o.
r h
(a)
Packaging M
If 4
(1) Model Nos.:
20-VS and 40-VS (4
h (2) Description g
,l Radiographic devices and shipping container for sealed sources. The e
g packages are approximately 12" high x 6" wide x 8" long.
The outer case is constructed of 15 gauge 303 stainless steel.
The package is si fi provided with a 0.76" diameter handle. The 34 pound uraniun shield is held in place by potting epoxy and 2 brackets within the case. The j-sealed source is held within a Zircaloy or titanium S-tube by a lockblock,
assembly and a safety plug assembly at the opposite end of the S-tube.
y The Model Nos. 20-VS and 40-VS are identical except for shielding
,5 y
capability of the uranium shield. The package weighs 42 pounds.
.E E
9l (3)
Drawings j
The package is constructed in accordance with Gulf Nuclear, Inc.
)
Drawing Nos. A-31, Sheets 3 and 4, Rev.1; A-31-1 Sheets 1 and 2, i
y Rev. 0; A-3-1, Rev.1; A-31-12, Rev. 0; A-31-16, Rev.1; A-31-18, Rev.
I i
1; A-31-20, Rev.1; A-31-21, Sheets 1, 2, and 3, Rev.1; A-31-31, Sheets 1, 2, and 3, Rev.1; A-31-32, Rev. 0; A-31-34, Sheet 3, Rev.1 l
and Sheet 4, Rev. 0; 1000-50-14, Rev. 0; and 1000-50-13, Rev. O.
g E
E i
01 I
i i
I I
P' I~g-l)IvIfJUUWQ mummmummmmmmmmmmum - m
}
l) fMMhilf/
APPENDIX -O-i:
,-.. _ ~.+.- -
, _. -. - -----=..-------,,
l j
T m.W.:..
z.:T.. h.T&T..2 Q 2'._ M n.7. W 1 9 ~..f_G"M.W
.;.2 _?"3_
4 s.
f' CONDITIONS h
4 4
- 9 Eocket 10.
-?'C:
h Da;e 2 - Certifica te 'e
?~
Persion.f;c. 6 9
s.
d b
n
?
h (b)
Contents 5
E (1)
Type and for of material F:
M F
Iridiun 192 sealed source which must be shown to meet the requirenents b
's of special fom radioactive material.
i; 3
i-d (2) tiaximum quantity of material per package F
E F
One source containing:
[.
(i) Model No. 20-VS package - 120 Ci; or
(
s d
(ii) Model No. 40-VS package - 220 Ci.
k U
'y 6.
The package model 6esignation rust be determined by the Initial Acceptance criteria given in Section 5.3 (p 5-3) of the application.
7.
The packages authorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 671.12.
I Gulf Nuclear, Inc. application dated January 8.
Expiration date:
April 30, 1989.
9 REFERENCES 21, 1984.
Supplenents dated:
March 6 and 20, 1984.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION p,
euaAL Charles E. MacDonald, Chie p*
Transportation Certification Branch
.h Division of Fuel Cycle and g
itaterial Safety, NMSS h
10 M Date:
' li s
E k
nF fi l
T_VEMMD.MM.M M.T.22ELNKTGKJC.N_J T2rU_T T y.v.y.
TROXLER ELE'CTRONIC LABORATORIES, INC.
P.O. BOX 12057, CORNWALLIS ROAD RESEARCH TRIANGLE PARK, NORTH CAROLINA 27709, U.S.A.
Telephone 919/549-8661, Cable.Troxelec, Telex 579474 TYPE A PACKAGE CERTIFICATION Troxler Electronic Laboratories, Inc, certifies that their models 1255, 1257, 1351, 1352, 2226, 2376, 2400 Series, 3205, 3216, 3200 Series, 3300 Series, 3400 Series, 3241, 3565 and 4640 contain Type A quantities of special for's radioactive materials and are packed for shipment in Specification 7A Type A containers.
These containers meet the requirements of United' States Department of Transportation CFR 173.24 and are designed and constructed to meet the standards as specified in CFR 173.403 and 173.465. These containers are marked and labeled in conformance with CFR 173.444. These regulations are in agreement with the Regulations for the Safe Transport of Radioactive Materials (Saf ety Series No. 6) of the International Atomic Energy Agency as A= ended.
A copy of this Certification must remain on file as required by CFR 173.415(a).
TROXLE ELECTRONIC LABORATORIES, INC.
G.
nneth Brown, Jr.
tation Safety Officer
=
m- -Eh APPENDIX -P-
F bMme. vp ux vomuNY';VIGVnUVWu
~
e.ee.
..e.
..ee e
ST E
- 11. 8 01-e ee
..eeeeeeesese..
....eeeeee.
173.378(a)(het, 1) Each s wippe r of specist foer radi oa t t i ve material shall maintain on file for at lease one wear after the Last saip* nt, and be prepared to provice t he 007, a co*Diete teetifica-tion and safety analysts that the spectat eoro sate-rial meets the reoutroents.
173.39 5 (a) SPECIAL TESTS, Special Foer matertal (1) FREE De D*
-- 1en f*ee fatts of da==v caosute. ho caeage.
Caosute esoeelenced randoa tweele cucinc fatt strikino at various angles upon contact. (caosute ss f urthee mounted within cevice and will not esperience esposure to outside in event of steiler free fall of actual finished cevice).
(2) PERCUS$10N -- Dummy capsule placed on 1/4" tead sheet on angle guice (toc concrete. Steel rod allowed to slice nown stuminu a 1"
off center) distance of 40". Five fatts with weLo*ent upright and five f alls with wetoment cown.ords. ho canage.
(3) NE ATIN3 -- Du==y capsule heates to red hot glo.
(1475 ceg F) with torch. Maintained for 10 einotes. Discoloration but no canage to capsule integrity.
(4) Im*ER$10N -- Dumey capsule placed in water breamer for 64 howes. he caeage.
This is to certify that the encapsulated radioactive materlat in CPN's gauge has been teste1 for and is in compliance with the reouireeents for s pe cial form saterial. It has been issued IAEA Certificate of Competent Authority ho. U$A/0115/$ by the US 007.
--- - J Juty 1,1985 CON Corc.
Wi ttia= mancuso Radiation Safety Cfficer PACKAGING 173.394(a)(1) Each shioper of a Specification 7A package must maintain oa file for a* Least one yea *
=
after the Latest shinee.t, and be prepared to pro-vice the
- DOT, a
complete certification and supporting saf ety analysis ceronsteating that the construction petboos, cackaging 'Jesign, and material of construction are in creptiance with the s pe ci f ic a t ion s.
CPN's gauFes c Dnt ain Radioactive MatePial in $DeCial form and as such must be packaged according to Specification 7A, iype A. The gauges are shipped in combination shipping and carrying cases made of high density polyethelene, ficeeglass or aluminun.
173.398(b) SPECIA'. TESTS for a Type A package (1) WATER $ PRAY== Esempt. Package is of plastic or petal.
t (ii) FREE DRO' -- Eneret. Package is of plastic or metat.
i (iii) CORNER DROS -- Esempt. Package is of plastic or metal.
(iv) PENETR AT10N== A steel rod 1.25 inches in diameter with hemi-spherical ends was drocped from a distance of 40 inches on to the centee of the top of the case. ho c ra c k ing or other significant deformation occured.
(v) ComeRES$10N -- Five loaded cases were stacked on top of a sixth case for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No visible Ceformation was observed.
This is to certify that the shipping case for CPN's gauge has been test-ed for and is in corptience with the requirements f or a Type IA, Type A packsoe.
4 1,
- -----W *fL*C July 1,1985 3
CPN Corp.
Williae Mancuso l
Radiation safety Officer M
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