ML20214V964
| ML20214V964 | |
| Person / Time | |
|---|---|
| Site: | 07100618 |
| Issue date: | 11/18/1986 |
| From: | Fortner G, Lloyd R, Scholla M MEMPHIS STATE UNIV., MEMPHIS, TN |
| To: | |
| Shared Package | |
| ML20214V951 | List: |
| References | |
| 27616, NUDOCS 8612100027 | |
| Download: ML20214V964 (7) | |
Text
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Quality Assurance Program for Shipment of Reactor Fuel, 10 CFR Part 71 QA Program APPROVAL RADIATION SAFETY SUBCOMMITTEE f/7 eW
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Quality Assurance Program for Shipment of Reactor Fuel, 10 CFR Part 71 QA Program 1.
Organization The final responsibility for the Quality Assurance (QA) Program for Part 71 Requirements rests with Memphis State University.
Design and fabrication shall not be conducted under this QA program.
This QA program is established to ensure compliance with 10 CFR 71 for the transportation of nine (9) fuel discs, sixteen (16) fuel cylinders, and one (1) core fuse (see attachment #1) from the Memphis State
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University Center for Nuclear Studies to a secure facility as designated by ther U.S.
Department of Energy.
The fuel contains a total of 663.56 grams of U-235.
The fuel is currently possessed by Memphis State University under NRC license number R-127.
The progra-is of limited duration and is designed for the disposition of e-unneeded existing inventory of reactor fuel.
The QA program is N
implemented using the existing MSU administrative organization show
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in Figure 1.
The Memphis State University Radiation Safety Office is responsible for overall administration of the program, training and certification, document control and auditing.
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The Radiation Safety Officer is responsible for handling, storing, shipping, inspection, test and operating status, and recordkeeping.
2.
Quality Assurance Program The Vice President for Advancement and Continuing Education J
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" ~ APPENDIX C IYYY~
Application for Amendment No. 5 ChMA.;;;
Operating License R-127, Docket 50-538 FUEL INVENTORY (SNM)
ITEM I.D. NO.
- GROSS WGT. (g)
SNM (g)
U-235 (g)
Core disc - 4 cm 20439 2138.9 495.32 98.28 Core disc - 4 cm 20440 2141.0 495.67 98.35 Core disc - 4 cm 20441 2027.2 468.05 92.87 Core disc - 4 cm 20450 2048.9 475.15 94.28 Core disc - 2 cm 20443 1259.8 291.10 57.76 Core disc - 2 cm 20444 1262.2 292.51 58.04 Core disc - 2 on 20445 1260.0 291.91 57.92 Core disc - 1 cm 20446 641.5 148,78 29.52 Core disc - 1 cm 20447 629.9 146.26 29.02 Core fuse 20106 5.93 2.02 0.40 CONTROL & SAFETY R0D FUEL CYLINDERS 4.7 cm dia.
20349 78.89 18.19 3.61 4.7 cm dia.
20350 79.01 18.24 3.62 4.7 cm dia.
20351 78.91 18.24 3.62 4.7 cm dia.
20352 78.91 18.24 3.62 4.7 cm dia.
20354 79.09 18.29 3.63 4.7 cm dia.
20358 79.02 18.29 3.63 4.7 cm dia.
20359 79.01 18.29 3.63 4.7 cm dia.
20360 79.10 18.29 3.63 4.7 cm dia.
20353 78.99 18.24 3.62 4.7 cm dia.
20355 78.92 18.24 3.62 4.7 cm dia.
20356 79.06 18.29 3.63 4.7 cm dia.
20357 78.98 18.29 3.63 2.3 cm dia.
20211 19.80 4.59 0.91 2.3 cm dia.
20212 19.89 4.59 0.91 2.3 cm dia.
20213 19.73 4.54 0.90 2.3 cm di a.
20214 19.78 4.59 0.91 TOTALS 14,442.42 3,344.21 663.56
- Gross Weight:
Fuel composition is UO2 in Polyethylene except for the core fuse which is U02 in Polystyrene.
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4 PRESIDENT MEMPHIS STATE Uti1VERSITY
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- iC".ITTEE DIRECTOR A3'.'A!iCEMEhi AND SECURITY AND C0?iTINUING EDUCATI0tt SAFETY SEP. VICES RADIATI0li SAFETY REACTOR FACILITY OFFICER.
SOUTH CAMPUS AND SECURITY FUEL STORAGE AREA 0FFICERS Direct Line of Authority
Advi sory/ Assistance Capaci ty FIGURE 1.
REACTOR FACILITY ORGANIZATION FOR " POSSESSION-ONLY" STA 17 w
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V Quality Assurance Program for Shipment of Reactor Fuel, 10 CFR Part 71 QA Program 1.
Organization The final responsibility for the Quality Assurance (QA)' Program for Part 71 Requirements rests with Memphis State University.
Design and' fabrication shall not be conducted under this.QA program.
This QA program is established to ensure compliance with 10 CFR 71 for the transportation of nine (9) fuel discs, sixteen (16) fuel cylinders, and one (1) core fuse (see attachment #1) from the Memphis State University Center for Nuclear Studies to a secure facility as designated by ther U.S.
Department of Energy.
The fuel contains a total of 663.56 grams of U-235.
The fuel is currently possessed by Hemphis State University under NRC license number R-127.
The program is of limited duration and is designed for the disposition of an unneeded existing inventory of reactor fuel.
The QA program is implemented using the existing MSU administrative organization shown in Figure 1.
The Memphis State University Radiation Safety Office is responsible for overall administration of the program, training and certification, document control and auditing.
The Radiation Safety Officer is responsible for handling, storing, shipping, inspection, test and operating status, and recordkeeping.
I 2.
Quality Assurance Program l
The Vice President for Advancement and Continuing Education
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establishes and implements this QA program.
Training, prior to loading and shipping, for all QA functions is made according to written procedures with Radiation Safety Subcommittee approval.
The QA program will ensure ~that all defined quality control procedures, engineering procedures, and specific provisions of the package design approval are satisfied.
The QA program will emphasize control of the characteristi,cs of the. package which are critical to safety.
Accidental. criticality is not a safety problem because the total U-235 is 663.56 grams.
The MSU Radiation Safety Office shall assure that-the radioactive material shipping package is designed and manufactured to
. meet the existing transportation regulations.
This requirement will be satisfied by using a DOT approved 6J shipping container.
- 3.
Document Control Documents related to specific packages and shipments are to be retained by the HSU Radiation Safety Office.
This shall include radiation surveys, cargo manifests, notes concerning labeling and sealing, Form 741, and all other information related to the control and accountability of the radioactive materials.
Documents and notes relating to security provisions will be retained by the Radiation Safety Office as well, i
- 4.
Handling and Loading 4
l The radioactive material is composed of 663.56 grams of enriched uranium suspended homogeniously in polyethylene except for the core f
fuse which is suspended in polystyrene.
All fuel elements have been i
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packed in DOT approved 6Jdrums.
There are 5 drums each of which contains less than 200 grams of U-235.
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Inspection
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. Prior to shipping, each container will be inspected to ensure all closures and seals are in place.
Each drum will be swipe tested-to ensure there is no external contamination.' Finally, each drum i
will be surveyed to verify radiation levels are condisten't with s
requirements of 10 CFR 173.417.
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Quality Assurance Records
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. t-Written procedures, checklists, equipment 1,i S t s, drawing and
. - t radiological survey data will be retained by the' Radiation Safetyi i..
Office.
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Audits
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l After the shipment is completed, an aydit will be performed in 1
accordance with written checklists.
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