ML20028H640
| ML20028H640 | |
| Person / Time | |
|---|---|
| Site: | 07100713 |
| Issue date: | 01/15/1991 |
| From: | UTAH STATE UNIV., LOGAN, UT |
| To: | |
| Shared Package | |
| ML20028H639 | List: |
| References | |
| NUDOCS 9101180087 | |
| Download: ML20028H640 (6) | |
Text
eins/91 OAs2 u or u c0LLEGE OF DGR SLC UT.
10.285 P003/009 I
UNIVERSITY OF UTAH QUALITY ASSURANCE PROGRAM FOR USE OF DOT SPECIFICATION 7A, TYPE A SHIPPING CONTAINERS REV I 15 JANUARY 1991 Submitted in Accordance with 10 CFR 71.14 /
i Licensee: The Regents of the University of Utah License No.:
R 25 Docket No.:
50 72 d
'Ihe University of Utah Nuclear Engineerin g Laboratory Department of Mechan. cal EnJineering Salt Lake City, UT 84 12 NOIISOo!k ON 3
C
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QUALITY ASSURANCE PROGRAM FOR USE OF DOT SPECIFICATION 7A, TYPE A SHIPPlNO CONTAINERS INTRODUCTION This Quality Assurance (QA) Program is for the use of new U.S. Department of Transportation (DOT) Specification 7A, Type A radioactive materials ship?ing containers for a one time shipment of sli thtly irradiated AGN 20lM nuclear reactor fue; to the U.S.
Department of Energy's (DO3) Y 12 Reprocessing Plant at Oak Ridge, Tennessee, for final disposition. The program under which these containers will be used is based on the following considerations:
(1)
The Universit of Utah Nuclear Engineering Laboratory (UUNEL) possesses twenty one (21) sli htly irradiated AON.201M fuel disks of various dimensions manufactured by Aerojet General Nucleonics, Corporation (defunct). The disks are enmposed of a homogeneous dispersion of 19.5% ennched UO in a pol ethylene matrix.
2 The fuel has a total U 235 content of 658.2 grams. The fuel was last irra isted in February 1985. Because the reactor was operated at very low power levels (maximum. licensed mwer was live watts) und generated an inconsequential amount of energy during its ifetime (approximately 247 watt hours), the activity of the fuel due to fission products has been determined to be negligible.
(2)
UUNEL is decommissioning its AON 20lM training and research reactor, U.S.
Nuclear Regulatory Commission (NRC) License No. R 25 (Docket No. 50 72), and must return the leased fuel to the DOE, the owner of the fuel. Shipment of the fuel material is being performed pursuant to the AON reactor operating license (R-25).
(3)
UUNF.L does not design, fabricate, assemble, or test radioactive material shipping containers, and does not intend to procure any containers for ownership or lease to others.
This QA Program is limited to the use of new DOT Specification 17H 55 gallon steel drums purchased by UUNEL as required DOE to accomplish the return of the fuel to DOR. These drums have been qualified as OT Speci0 cation 7A, Type A packaging.
The QA Program is submitted pursuant to 10 CFR 71.14,10 CFR 71.101, and 49 CFR 173. The Program outline follows NRC Regulatory Guide 7.10.
1.
ORGANIZATION The Director of the Nuclear Reactor Laboratory (DNEL) is the Administrative Officer responsible for the tractor facility and its operation, maintenance, and safety. The DNEL l
reports to the President of the University and is advised in all matters concerning health and safety y the Radiation Safety Committee. He is advised in all matters concerning reactor safety y the Reactor Safety Committee (RSC).
The Radiation Safety Officer (RSO) is the head of the Radioloolcal Health Department (RllD) and is responsible for the safe use and disposal of radioactive material at the University. The RSO administers the University's radiation safety program and provides technical assistance to the Radiation Safety Committee and the RSC (the RSO serves ex n//irio as a member of each committee and reports to the Vice President for Research). The RSO is authorized and directed to promulgat: and enforce such procedwes as are necessary
01/16/91 09:53 U OF U COLLEGE OF EtGR SLC UT.
NO.295 P005/008 to assure compliance with applicable federal and state replations and to ensure the accurate interpretation and effective implementation of the pol.cles and rules established by the Rtuliation Safety Committee.
1 The RSC is responsible for independent reviews and audits of UUNEL facility operations to insure that all operations are performed in a safe and competent manner within the requiremer.ts of the NRC and advises the Vice President for Research in all matters related to reactor and personnel safety. The RSC holds periodic meetings and has the authority to conduct reviews and audits of facility operations.
The DNEL is responsible for establishing and implementing the_ quality assu. nee plan for the shipment of the AON fuel. The DNEL willidentify quality problenv. ecommend solutions, and ve '
implementation of such solutions. He will establish and :arry out a checklist system of anned audits and surveillances to verify compliance with ah tspects of the QA program and to determine its effectiveness. He will keep accurate, detiJled, and auditable records of his activitics during the shipment process.
2.
Q.UALITY ASSURANCE PROGRAM The scope of the program includes purchasing, handling, loading, and delivering to a DOE-approved carrier for transport: U.S. Nuclear Regulatory Commission (NRC) approved DOT Specification 7A, Type A radioactive material shipping containers for return of AON fuel to the DOE facility at Oak Ridge. The quantity of material to be shipped is fixed.
Since the return of the fuel represents a one time action, the active portion of the program will span a period of no more tbtn a few days.
Quality Control (QC) will be exercised primarily through the use of written procedures derived from: (a) federal regulatory requirements; (b) DOE's instructions, procedures, and drawings; and (c) a licable portions of the University's radiation safety procedures. QA will be effected b ormatting those procedures as written checklists to be used b ' the individuals or thei designates who are responsible for quality assurance. A QA audi will be perfonned at the conclusion of the shipment.
3.
PROCUREMENT AND FABRICATION Documents for procurement of the containers shall require the supplier to provide certification that manufacture of the containers was aerformed pursuant to a quality assurance program in conformance with 10 CFR 71. 09 and 49 CFR 173.474. This certification shall describe the manufacturer's QA program in detail. A checklist of use documents willinclude: (a) the manufacturer's certification of QA compliance; (b) DOE's instructions for handling and use of the container; and (c) DOE's provision of other revised or pertinent documentation such as certification of compliance, as built drawings, sketches, technical reports, and use manuals.
- 4. INSTRUCTION
S. PROCEDURE
S. AND DRAWINGS 4.1 Preparation of Packaging for Use. The routine determinations of 10 CFR 71.87, where applicabic, will be subject to checklist assurance.
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Nb,IEh IO0600h 4.2 Repair, Rework and Maintenance. UUNEL will not undertake repair, rework, or maintenance. Servicing, such as gasket replacement, shall be in accordance with DOE's specifications.
4.3 Londing. Loading shall be conducted in accordance with a written plan of sufficient specificity to identify and quantitatively account for the SNM conforrning to shipping papers and inventory change reports. Surveys of radiation fields and surface contamination of the package shall be made and recorded.
4.4 Transport of Package Upon delivery of the package to a carrier for transport, the condition of the package, as evidenced by visual inspection will be noted; the seals and labels will be recorded along with package identification and license registration numbers.
A written checklist procedure will be used.
5.
DDCUhiENT CONTROL Control shall be exercised over the following documents:
(1)
Document checklist.
(2)
Operating procedures.
(3)
Inspection procedures.
(4)
Loading plans.
(S)
Documentatior' provided by DOE that relate to certifications, QC and QA.
(6)
Radiation survey results.
(7)
Shipping papers, procedures and checklists, and changes thereto are to be approved by either the DNEL, RSO, or their designates.
6.
CONTROL OF PURCHASED MATERIAL. EOLTIPMENT. AND SERVICES The only materials to be purchased with regard to this transfer ute three.(3) new DOT Specific:ttion 17H singletrip shipping containers, heads, gaskets, t.nd packing material as required to complete this shipment, ho other special puraose materials oreopment are to be aurchased for this activity. Services, such as licenset carrier transport u a ue arranged by DOE traffic offices.
7.
IDENTjFICATION AND CONTROL OF MATERIALE. PARTS. AND CQh1PONENTS Section 4.2, above, is applicable here, 8.
SPECIAL PROCESSES No special processes are to be undertaken under this program.
9.
INSPECTION CONTROL 9.1 Receipt Inspection. Inadequately identified packaging, or packaginf, which deviates significantly from certification, drawings, or specifications, will not se used unless or until corrected by DOE.
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9 9.2 Maintenance. Maintenance other than prescribed servicing will not be performed by UUNEL.
9.3 FinalInspections. Checklists will be established to assure:
(1)
Package is properly assembled.
(2)
Moderators and/or neutron absorbers are present if required.
(3)
Shipping papers are properly com eted.
(4)
Package is conspicuously and dur bly marked as required by the DOT.
(5)
Pre and post loading radiation surve Finalinspection has )een completed.ys have been completed.
(6) inspection is to be certified by the RSO or his designated alternate.
10.
PROTECTION TEST CQNTROL 10.1 Use of Packages. Tests permitted, recommended, or specified by DOE will be used to establish a QA checklist.
10.2 Rudiation survey results are to be compiled and records maintained by the
- 11. CONTROL QF MEASURING AND TEST EOUIPMENT UUNEL will perform all tests or inspections, as required by DOE. Radiation survey equipment shall be maintained and calibrated in accordance with nomial procedures of the Univet sity of Utah Radiation Safety Policy Manual.
- 12. IJANDLING. STORAGE. AND SHIPPING 12.1 Handling and Storage. Special handling and lifting equiament will be used in accordance with equipment specified or provided by DOE, and accorc ing to conditions and instructions provided by DOE. See sections 4,5, and 6, above. The containers will be loaded and promptly shipped to Oak Ridge as soon as practicable. The containers will be maintained in protected storage until used.
12.2 Preparation for Release and Shipment. Measures will be taken to ensure that:
(1)
Cavities are dry.
(2)
Specified operations, inspections, and tests are verified by written checklists.
(3)
The RSO is responsible for observance of NRC and DOT requirements, and for the preparation of the shipping papers.
Quality Anurance will be performed with written checklists.
- 13. INSPECTION TEST. AND OPERATING STATUS
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" Status is to be tracked by a master checklist that ccknowledges checkoff of individual checklist completion.
14
. CONTROL OF NONCONFORMINO MATERIALS. PARTS OR COMPONENTS Not applicable. Records, repair, maintenance, or modification are not to te undertaken by U UN EL.
- 15. CORRECTIVE ACrlONS b
It is the responsibility of the UUNEL QC/QA Program to report conditions detrimental to quality to DOE, who will be responsible for any corrective actions required, I 6.
QLBLLTY ASSURANCE RECORDS
{
Records showing evidence of delivery to a carrier under NRC and DOT requirements shall be retained for a minimum of one year, except for SNM transfer and inventory records retained for the duration on NRC licensing over the University of Utah Broad Scope 1.icense. Records are to be retained by the Radiological Health Department (RILD), which is also responsible for maintaining all University records relating to perronnel exposures, radioactive material releases and shipments, ani related radiation protection matters.
Records will be retained for a period of three (3) years following date of shipment, as required by 10 CFR 71.91(c).
17.
AUDITS _
The activity covered by this shipping program is a shon term effort. Selected members of the RSC will perfonn a close out audit to determine the adequacy of the records generated under this program. This audit will be performed according to a written checklist.
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