ML20126B066
| ML20126B066 | |
| Person / Time | |
|---|---|
| Site: | 07106717, 07109135, 07100166 |
| Issue date: | 05/01/1985 |
| From: | Mattingly M MATTINGLY TESTING SERVICES, INC. (FORMERLY MATTINGLY |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25238, NUDOCS 8506130559 | |
| Download: ML20126B066 (9) | |
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May 1, 1985 File //850035 Reference Request for Registration Director, Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Cornission f[If
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Washington, DC 20555 Gentlemen:
44 This correspondence refers to certificate users other than Gam:ra Industries, Baton Rouge, IA to register Mattingly & 0'Reilly Services and Testing, Inc as a certificate holder and user for certificate numbers USA /9135/B(U)T Revision 0, USA /6717/B(U)T Revision 1, and USA /0166/S Revision 4.
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-We - equest registration of Mattingly & 0'Reilly Services and Test ng, Inc as a user and shipper of radioactive material. Please list Mr.
Mark M. Mattingly for approval.
Copies of the certificates attached.
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Radiation Safe Officer
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, g' U.S. NUCLEAR RECUL, AY COMMISSION
- 1. APPRO AL r UMBER t,.a n OUALITY ASSURANCE PROGRAM APPROVAL REviSi N w{sra FOR RADIOACTlvE MATERIAL PACKAGES 14 4
g Pursuant to the Atomic Energy Act of 1954,as amended.the Energy Reorganization Act of 1974.as amended.and Title 10. Code of Federal y
Regulations. Chapter 1. Part 71 and in reliar ce on staternents and representatrons heretofore rnade in item $ by the person named in item k
- 2. the Quality Assurance Program identified in item 5 is hereby approved. This approvalis issued to satisfy the requirements of Section k
71.101 of 10 CFR Part 71. This approvalis suoject to all apphcable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
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2 Nr.ME 3 EXPIRATION DATE Garmia Industries February 28, 1990 STREET ADDRESS
- j 2555 Ted Dunham Avenue a oOcxETNUueEA CITY STATE r
i Baton Rouge LA ZIPI[)Sf22 71-0010 S OUALITY ASSURANCE PROGRAM APPLICATION DATE(S) i January 30, 1985 6 CONDITIONS i
4 A.
Activities conducted under applicable criteria of Subpart H of
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10 CFR Part 71 to be executed with regard to transportation packages.*
4 B.
This spproval is lirnited to sealed sources.
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'h FOR THE U.S. NUCLEAR REGULATORY COMMISSION h:
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q Charles E. HaCDonald yEB 12 m
{ CHIEF. TRANSPORTATION CERTIFICATION OR ANCH DATF
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G US Depor1 ment c.,ose,,.,
s.... s w W.wyn D c 7ewa of Transpo to!on Research and Special Programs IAEA CERTIFICATE OF COMPETENT AUTHORITY Type B Radioactive Materials Package Design Certificate Number USA /9135/B(U)T Revision 0 This establishes that the packaging design described herein, when loaded with the authorized radioactive contents, has been certified by the National Competent Authority of the United States as meeting the regulatory requirements for Type B packaging for radioactive materials as prescribed in IAEA Regulatiop and in accordance with 49 CFR Sections 173.393b and 173.394(b)(3) of the USA Regula-tions for the transport of radioactive materials.
I.
Package Identification < Model Nos:
Century S, Century SA, Century Universal S, and Centry Universal SA.
Pachaging Description - Packaging authorized by this certificate consists II.
of a zirca,lloy or titanium "S" tube which is surrounded by depleted uranium shielding which is encased in an outer steel housing. The void between the shielding and housing is filled with polyurethane foam.
External dimensions are 7.0 inches long by 5.5 inches in diameter with a gross weight of 45 pounds.
III.
Authorized Radioactive Contents - The authorized contents consist of special form encapsulations meeting the requirements of 49 CFR 173.389(g) and containing not more than 120 curies of iridium-192.
Contents must be of a design wijich has been tested and demonstrated to be leaktight to a sensitivity of 10
- atm-cm /see or less.
IV.
General Conditions -
a.
Each user of this certificate,must have in his possession a copy of this certificate.
b.
Each user of this certificate, other than Gamma Industries, Baton Rouge, LA shall register his identity in writing to the Office of Hazardous Materials Regulation, Materials Transportation Bureau, U.S. Department of Transportation, Washington, D. C. 20590.
c.
This certificate does not relieve any consignor or carrier from compliance with any requirement of the Government of any country through or into which the package is to be transported.
Certificate Number USA /9135/B(U)T, Revision 0 Page 2 V.
Marking and Labeling - The package must bear the marking USA /9135/B(U) as well as the other marking and labels prescribed by the USA Regulations.
VI.
Expiration Date - This certificate, unless renewed, expires on April,30, 1987.
This certificate is issued in accordance with the requirements of the IAEA and USA Regulations and in response to the June 21, 1982 petition by Gamma Industries, Baton Rouge, LA and in consideration of the associated information provided in U.S. NRC Certificate of Compliance No. 9135 (Appendix A) and related corre-spondence.
i Certified by:
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Richard R. Rawl Date Chief, Radioactive Materials Branch Office of IIazardous Materials Regulation Materials Transportation Bureau t
I" Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, 1973 Revised Edition" published by the International Atomic Energy Agency (IAEA),
1 Vienne, Austria.
2Title 49, Code of Federal Regulations, Parts 100-199, USA.
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'm sem sireet. s w US Dtemt Washegton. O C 20590 gg Research and Speclol Programs Administrutton IAEA CERTIFICATE OF CO!PEIHE JUDORITY Type B Radioactive Materials Package Design Certificate Number USA /6717/B(U)T (Revision 1) n is establishes that the packaging design described herein, when loaded with the authorizcd rulimtive contents, has been certified bf the National Competent Authority of the United States, as neeting the regula-tory requirements for Type B packaging for radioactive naterials as pre-scribed in IAEA 1/ Ibgulations and SS 49 CFR 173.393a and 173.394(b)(3) of the USA 2/ Ibgulations for the transport of radioactive naterials.
I.
Package Identification - Pedel No. 6717-B.
II.
Packaging Description - Packaging authorized b this certificate consists f
of an outer 10-gallon steel drun with an inner container which is a netal-walled -
container meeting the requircments of Dar Specification 7A, surrounded by polyurethane filler and a 1-1/2" asbestos free liner. Gross weight is approximately 75 pounds.
III. Authorized Radioactive Contents - The authorized contents consist of radioactive materials, n.o.s,. as not nore than 200 curies of iridium-192 as scaled sources which must meet the requircments for special form.as set forth in 49 CFR 173.389(g).
Contents must be of a design whicg has been tested and dmonstrated to be leaktight to a sensitivity of 10- atm-cc/sec or less.
IV.
General Conditicns -
a.
nch user of this certificate must have in his possession a copy of this certificate.
b.
Each user of this certificate, other than Ganma Industries, Baton Ibuge, Iouisiana, shall register his identity in writing to the Office of Hazardous Materials Regulation, U.S. Department of Transportation, Washington, D.C.
20590.
c.
nis certificate does not relieve any consignor or carrier frcin c:xrpliance with any requircment of the Goverrment of any country through or into which the package is to be transported.
V.
terkirri and Labeling - ne package cust bear the narking USA /6717/B(U) as 611 as the other nurking ard labels prescribed by the USA Pegulations.
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Elr Certificate Nxnber USV6717/B(U)T (Rev.1)
Page 2 VI.
Dcpiration Date,- This certificate, unless renewed, expires cn July 31, 1985.
This certificate is issuea in accordance with the requirements of the IAEA and USA Begulations and in response to the mrch 5,1982 petition by Ganma Industries, Baton Rouge, Iouisiana and in consideration of the associated information provided in U.S. Nuclear Regulatctnf Cmmission Certificate No.
6717 (Appendix A) and related correspondence.
Certified by:
Sn dozf6/W2 R. R. RAWL l
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Chief, Radioactive Materials Branch Office of Hazardous Materials Pegulation Materials Transportation Bureau 1/ " Safety Series No. 6, Pegulations for the Safe Transportation of Radioactive
'~ Materials," 1973 Fevised Edition published by the International Atcznic Energy Agency (IAEA), Vienna, Austria.
2/ Title 49, Code of Federal Regulations, Parts 100-199, USA.
Bevision 1 issued to corrcct package description.
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US Deportment ex se,enn, si.es. su Of Transporrotion
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 If and USA 2/ regulations for the transport of radioactive materials.
I.
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 YD(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.
II.
Radioactive Contents - The authori' zed radioactive contents of these sources consist of not more than:
a 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 _-_ 9.2_
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Cobalt-60 Ytterbium-169 fron-59 Zinc-65
2 Certificate Number USA /0166/S, Revision 4 11.
Radioactive Contents (continveM Model No. (cont'd)
Contents (cont'd)
NB, NBG and NB(HP) 25 Curies Americium-241 30 millicuries Ra-226 500 millicuries Americum-241 and Cesium-137 mixture Single Encapsulation Universal Soruce 500 curies Iridium-192 20 curies Cobalt-60 Double Encapsulation Universal Source 5000 curies Iridium-192 2000 curies Cobalt-60 Single $ncapsulation Side Weld 500 curies Iridium-192 20 curies Cobalt-60 i
III.
This certificate, unless renewed, expires July 30,1987.
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,
- 1.ouisiana, and in consideration of the associated information therein.
Certified by:
kaL/3lW4 Richard R. Rawl
(@te) U Chief, Radioactive Materials Branch Office of Hazardous Materials Regulation Materials Transportation Bureau 1/ " Safety 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, USA.
Revision 4 issued to correct materials of construction specification.
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w NRC LICENSE #25-21479-01 MAY 1, 1985 QUALITY ASSURANCE PROGRAM
- 1. ORGANIZATION The ultimate responsibility for the QA Program in accordance with Part 71 requirements rests with Mattingly & 0'Reilly Services and Testing, Inc.
Design and fabrication shall not be accomplished under this QA Program.
The Assistant Radiation Safety Officer is designated as the responsible individual for Part 71 quality assurance requirements.
The Radiaton Safety Officer is responsibile for the overall administration of the QA Program and for training and certification. The Assistant Radiation Safety Officer is responsible for document control and audits.
The Radiographers are responsible for handling, storing, shipping, inspection, test and operating status, and record keeping.
- 2. QUALITY ASSURANCE PROGRAM
~ The management.of Mattingly & 0'Reilly Services and Testing, Inc. establishes and impliments this QA Program. Training prior to performing QA activities is required in compliance with written procedures. Revisions to the QA Program shall be made in accrdance with written procedures and with management approval. The QA Program will ensur'e that all defined QA Procedures, engineering procedures, and specific provisions for package design approval are satisfied.
The QA Program shall emphasize control of characteristics of the package, which are critical to safety.
The Assistant Radiation Safety Officer 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 and fabricated after 1 January 1979. This requirement may be satisfied by receiving a certification to this effect from the manufacturer and/or supplier.
- 3. DOCUMENT CONTROL All documents related to a specific shipping package shall be controlled through the implementation of written procedures. All document changes shall be accomplished in compliance with written procedures approved by management.
The Radiation Safety Officer shall assure that all QA functions are conducted in compliance with the latest applicable changes to these documents.
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- 5. INSPECTION, TEST AND OPERATING STATUS Inspection, test, and operating status of packages for rtain radioactive material will be indicated and controlled by written procedures. The status shall be indicated by tag, label, marking, and/or log entry. The status of nonconforming parts and/or packages shall be maintained in compliance with written procedures.
Radiographers shall perform the Con 2nission's required inspections and tests in accordance with written procedures. The Radiation Safety Officer shall assure that these activities are performed.
6.~ QUALITY ASSURANCE RECORDS Records of package approvals (including references and drawings) procurement, inspections, tests, operating logs, audit results, personnel training and qualifications, and reco ds of shipments shall be maintained. Descriptions of equianent and written procedures shall also be maintained, a) The records will be maintained in accordance with a written procedure.
b) The records will be identifiable and retrievable.
c) The Radiation Safety Officer shall maintain a list of the records and their storage location.
- 7. AUDITS An established schedule for audits of the QA Program shall be implemented in conducting audits using written procedures and/or check-lists. Results of audits shall be n:aintained. Audit reports shall be evaluated and deficient areas shall be corrected. The audits shall be dependent on the safety significance of the activity being audited, but each activity shall be audited at least once each year. Audit reports shall be maintained as a part of the quality assurance records.
The Auditor shall not have direct resposibility for the activity oeing audited.
Mark M. Mattingly Radiation Safety Officer Mattingly & 0'Reilly Services and Testing, Inc.
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