ML20211N767
| ML20211N767 | |
| Person / Time | |
|---|---|
| Site: | 07100575 |
| Issue date: | 01/31/1987 |
| From: | Brigham Young University, PROVO, UT |
| To: | |
| Shared Package | |
| ML20211N757 | List: |
| References | |
| NUDOCS 8703020216 | |
| Download: ML20211N767 (8) | |
Text
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f Brigham Young University Quality Assurance Program Submitted in Accordance With 10 CFR 71.12 (b)
Licensees Brigham Young University License R-109 Brigham Young University Provo, Utah 84602 January 1987 0703020216 870123 PDR ADOCK 07100575 PDR C
T Quality Assurance Program for Use of Type B( )F Containers Introduction Attendant to the shipment of 1502 grams of uranium enriched in the isotope U-235 Brigham Young University- (BYU) submits a Quality Assurance-Program for the use of a number of NRC certified Type USA /9009/B(
)F (Model FL-10-1) containers suitable for the shipment of liquid fuel.
The program under.which these containers will be used is based on the following considerations:
(1) BYU possesses approximately 30 liters of uranium fuel enriched with 1502 grams of the isotope U-235.
(2)
BYU wishes to return this fuel to the Department of Energy.
(3)- The fuel produces a radiation field of -approximately 10 mrem per hour at the surface of the core of the reactor.
(4) BYU possesses no other liquid fuel, and this Program is limited to the objective (2),
the quantity indicated in (1), with the characteristics indicated in (3).
(5) BYU does not design, fabricate, assemble, or test containers, and does not intend to procure any container for ownership or lease to others.
This OA Program is limited to the use of containers to accomplish (2).
BYU does not intend to rework, repair, maintain or modify the containers.
The OA Program is submitted pursuant to 10 CFR part 71, paragraphs 71.12 and subpart H.
The Program outline follows Regulatory Guide 7.10 (January 1983) in those parts of Annex 2 that are applicable to leasing and use of Type USA /9009/B( IF (Model FL-10-1) containers.
- 1. Oroanization There is no formally established overall Quality Assurance organization at BYU. Figure 1 illustrates existing organizational relations within which QA is performed to the necessary extent.
The use of the USA /9009/B( )F (Model FL-10-1) packaging will be performed largely by the reactor operating group and a radiation safety officer, i.e. four people, including the reactor chief.
Quality Control and Quality Assurance records are created at this level, but will be retained by the Radiation Safety Officer (RS0) following the dissolution of the reactor group.
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. The DC and QA activities are divided between the reactor group and the RSO. The reactor chief is responsible for the QC and QA of obtaining,. handling, and loading of the packaging. The Radiation Safety Officer is responsible for the DC and QA of radiation activities related to protection.
The Radiation Safety Committee (RSC) plays an active role in reactor dismantlement and fuel shipment planning.
RSC membership
' includes the Director of Campus Safety, the Assistant Dean of the College of Biology and Agriculture, a Senior Reactor Operator, and the Campus Radiation Safety Officer.
- 2. Quality Assurance Prooram i
The scope of the program includes obtaining, handling, loading, and delivering to a
carrier for transport; NRC approved USA /9009/B( )F (Model FL-10-1) containers for return of reactor fuel to the Department of Energy.
The quantity of material to be shipped i
is fixed (30 liters of fuel solution and approximately 3 liters of rinse solution).
BYU wishes to return this material to the DOE, and consequently the active portion of the program will span a period of no more than a few months.
Quality Control will be exercised primarily through the use of written procedures constructed from: (a) federal regulatory requirements; (b) container owner's instructions, procedures, and drawings; and (c) applicable portions of campus radiation protection procedures. Quality Assurance will be effected by formatting those procedures as checklists to be used by the individuals or their designates who are responsible for quality assurance.
- 3. Desion Control The agreement is to include the owner's certification that the design was accomplished under control of an NRC-approved QA Program.
- 4. Aoreement Document Control 1
A check list of documents will includes (a) the owner's certification of item 3.
above; (b) the owner's instructions for handling and use of the container; and (c) the owner's provision of other required or pertinent documentation such as the certificate of I
compliance, as-built drawings, sketches, and use manuals.
- 5. Instructions. Procedures, and Drawinos 5.1 Preparation of Packaging for Use.
The routine determinations, 10 CFR 71.87, where applicable, will be subject to check list assurance. Subparagraph (h) and 10 CFR 71.45 are to be satisfied by owner's certification.
. 3.2 Repair, Rework, and Maintenance.
BYU will not undertake
- repair, rework, or maintenance.
Servicing, such as gasket replacement, shall be in accordance with owner's specifications.
5.3 Loading.
Loading shall be conducted under a plan of sufficient specificity to identify and account for quantities of fuel conforming to shipping papers and inventory change reports. Surveys of radiation fields and surface contamination of the package shall be made and recorded.
5.4 Transport of Package.
Upon delivery of packages 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 by model and license registration numbers. A check list procedure will be used.
6.
Document Control Control shall be exercised over the following documents:
(1) Document check list (2) Operating procedures (3)
Inspection procedures (4) Loading plans (5) Documents provided by owner of the containers that relate to certifications, QC and QA (6) Radiation survey results (7) Shipping papers Procedures and check lists, and changes thereto are to be approved by either the Reactor Chief, the Radiation Safety Officer, or their respective designates.
7.
Control of Purchased Material. Eautoment, and Services No special purpose materials or equipment are to be purchased for this activity.
Services such as container off-loading, on-loading, and carrier transport will be procured via normi'.
university procedures, with the Reactor Chief's approval of initiating documents.
8.
Identification and Control of Materials. Parts, and Components.
Section 5.2 is applicable here.
9.
Special Processes No special processes are to be undertaken under this program.
. 10.
Inspection Control 10.1 Receipt inspection.
Inadequately identified packaging, or packaging which deviates significantly from certifications, drawings, or specifications, will not be used unless or until corrected by owner. Containers are to be dry upon receipt, and if not dry, will be dried prior to loading.
10.2 Maintenance. Maintenance other that prescribed servicing will_not be performed by BYU.
10.3 Final Inspections.
Checklists will be established to ensure that:
(1) Packages are properly assembled.
(2)
Moderators and/or neutron absorbers are present if required.
(3) Shipping papers are properly completed.
(4) Packages are conspicuously and durably marked as required by DOT.
(5)
Pre-and post-loading radiation surveys have been completed.
(6) Final inspection has been completed.
Inspection is to be jointly certified by the Reactor Chief and the Radiation Safety Officer or their designated alternates.
11.
Test Control.
11.1.
Use of Packages.
Tests permitted, recommended, or specified by owner will be used to establish a OA check list.
11.2.
Radiation survey results are to be compiled and records maintained by the Radiation Safety Officer.
12.
Control of Measurino and Test Ecutoment.
As a user, BYU does not expect to use gauges, fixtures, reference standards, or other devices used to measure product (container) characteristics.
Radiation survey equipment shall be maintained and calibrated in accordance with normal procedures of the BYU Radiation Safety program.
13.
Handlino. Storace, and Shippino.
13.1 Handling and Storage.
Special handling and lifting equipment will be used in accordance with equipment specified or provided by the owner, and accordir.g to conditions identified in a certificate of compliance as well as instructions provided by the owner. See paragraphs 4, 5, and 6.
Containers will be used promptly and returned to owner; they will not be placed in storage.
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i 13.2 Preparation for Release and Shipment. Mcasures will.be,
instituted to ensure that
(
(1)', Cavities are dry (sef Jaragraph 10.1)
(2) Specified operations, inspections, and tests, are verified by check lists.
(3)
All NRC and DOT requirements a(e observed and tbs appropeicte shipping papers are 'pr2 pared.
This will be the responsibility of the Reactor Chief.
Quality Assurance will be performed with check lists.
4 14 Inspection. Test, and Doeratino Status.
StatusistobetrackedbyamasterchecklisNthatacknowledges check-offofir.dividualchecklistcompletijr.
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. e 15.
Control of Nonc.Qnformino Materials. F: fry,3.
o*> Components.
1 s
Not applicable., Rewo.r k, repair, maintenasce, or mcdification are not to be undertaken by BYU.
16.
Corrective Actions.
16.1 Reperting.
It is the responsibility of BYU QC/DA to report conditions,de{rimental to cua:1\\y to the owner.
16.2 Closecut.
DYU as a user will deem closcoat completed upon (a) correction of the condition by owner, or (b) owner's withdrawal of the container ferm service.
17 Quality Assuranct Records..
Records showing evidence of delivury of packages to a carrier under NRC and DOT requirements,.shall be retained for,4 minimum of one year, except for SNM transfer'.ind inventory records reta'ined for the duration of NRC licensing authority. Records are to oe retained by the Radiation Eafety Office, which is also responsible for maintaining _, all s 9YU records relating to personnel exposures, radioactive; material releases and shipments,.' and related radiation protectiorfmattars.
18.
Audits.
The activity covered by this OA Program is a shE(t-term effort.
The Radiation Safety Committee shall appoint a representative to perform a closecut audit to determine the adequacy of the records generated under this program.
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Figure 1.
Organizational relations within which QA is per. formed.
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Associate Academic Vice President ~
Brigham Young University Radiation Safety Committee S-Reactor Chief h
L Senior Reactor Radiation Safety Technician
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Operator Officer
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