ML20137V389

QA Program for Shipment of Unirradiated Research Reactor Fuel

ML20137V389
Person / Time
Site:	07109134
Issue date:	11/08/1985
From:	PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA
To:
Shared Package
ML20137V379	List: ML20137V375 ML20137V389
References
NUDOCS 8512090538
Download: ML20137V389 (5)

Text

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Quality Assurance Program for Shioment of Unirradiated Research 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 The Pennsylvania State University (PSU).

Design and fabrication shall not be conducted under this QA program. This i

QA program is established to ensure compliance with 10 CFR 71 for the transportation of seven (7) unused aluminum clad uranium-aluminum alloy fuel elements from the Penn State Breazeale Reactor (PSBR) to a secure facility to be designated by the U.S. Department of Energy. The seven elements contain a total of less than 700 grams of U-235. These fuel elements are currently possessed by the PSBR under NRC license number R-2.

The program is of limited duration and is designed for the disposition of a non-replenishable existing inventory of these unused reactor fuel elements. The QA program is implemented using the organization shown in Fig. 1.

The. University Health Physics Office is responsible for overall administration of the program, training and certification, document 1

control and auditing.

The Director of the PSBR is responsible for handling, storing, shipping, inspection, test and operating status, and recordkeeping.

f 2.

Quality Assurance Program The Director of the PSBR establishes and implements this QA Program.

Training, prior to loading and shipping, for all QA functions is made l

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Vice President for Research and Dean of the Graduate School Dean, College of Engineering Director of Inter College Research Programs Nuclear Engineering Department Head University Health Penn State Reactor Physics Safeguards Committee l

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I Director

[ _, _ _ _ _ _ Penn State Breazeale Reactor ___j Reactor Staff Figure 1.

Organization Chart for The Pennsylvania State University Breazeale Reactor.

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according to written procedures with PSBR management approval. The QA Program will ensure that all defined quality control procedures, j

engineering procedures, and specific provisions of the package design approval are satisfied. The QA Program will emphasize control of the characteristics of the package which are critical to safety. Accidental criticality is not a safety problem because the total U-235 is less than 700 gms.

The PSU Health Physicist shall assure that all radioactive material I

shipping packages are designed and manufactured to meet the existing i

i transportation regulations. This requirement will be satisfied by f

checking the package against the NRC Certificate of Compliance and the 4

associated references, i

3 Document Control Documents related to specific packages and shipments are to be retained by the PSU Health Physics Office. This shall include radiation i

I surveys, cargo manifests, notes concerning labeling and sealing, Form 741, and all other information related to the control and accountability of the f

radioactive materials.

Documents and notes relating to security provisions will be retained by the PSBR management.

4.

Handling and Loading The radioactive material is enriched uranium alloyed with aluminum and encapsulated by aluminum cladding in the form of 7 MTR type fuel elements. Two of these elements are control elements with fuel plates missing to provide space for control rods. The other five are partial

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elements. The maximum U-235 in any one element is less than 134 gms.

Written instructions will be provided for proper placement of each fuel element in the inner container and for proper blocking to maintain each element in proper placement with respect to the cadmium liner.

5.

Inspection Prior to use, the shipping container will be' opened to determine operability of closures, to visually inspect the integrity of the structure, and to provide access for interior swipes.

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6.

Quality Assurance Records-

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Written procedures, checklists,"e'kiiipm'entl'ists, drawings and radiological survey data will be retained b.y the Health Physics Office.

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Audits

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After the shipment is completed 'an'sudit will be performed in il i

^ 5 accordance with Written checklists.

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