ML20044E093

Application for Renewal of QA Program Approval for Radioactive Matl package:0680

ML20044E093
Person / Time
Site:	07100680
Issue date:	05/10/1993
From:	Marlone Davis OHIO STATE UNIV., COLUMBUS, OH
To:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9305210266
Download: ML20044E093 (1)

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T-H - E office of nadiation safety B-042 craves Ha!!

333 West 10th Avenue Columbus, OH 43210-1239

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Phone 614-292-0122

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UNIVERSITY May 10, 1993 Mr. Charles E. MacDonald, Chief

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Transportation Branch Division of Industrial and Medical Nuclear Safety, NMSS

Dear Mr. MacDonald :

It has been brought to our attention that approval for our Radioactive Material Packages Quality Assurance Program No.

0680 is approaching expiration. We would like to formally request that approval for this program be renewed. We are hoping to use the BMI-1 shipping cask within the next year to ship reactor fuel to a DOE Facility. Enclosed are copies of the original QA plan and latest approval. The hand written notes on the QA plan are notes that I made in June of 1992 that reflect the fact that at that time, we wanted to use the BCL-4 cask for shipping Co-60.

We believe that we are exempted under 1G CFR 170.11 (a) (4) from the $250.00 application fee, as we are a non-profit educational institution.

Sincerely,

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L,i h un Michael J. Davis Senior Reactor Operator Enclosure cc: Mr. Richard D. Myser 1

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Engineering Expenment Station IC '-iitchcoch Han TJT 2070 Neil Avenue I

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I i UNIVERSITY l August 7, 1989 Mr. Len Gcrden Transportation Divisicn Nuclear Reactor Commission 11555 Rockville Pike Mail Sten 4E4 Rockville MD 20852 SU5 JECT:

Q.A. Program Used in She Transport of Radioactive Materials for The Ohio State University Research Reactor Docket #71-0680

Dear Mr. Gorden:

Based on conversations between you and Richard Myser of the 05URR, we have revised our Q.A. Plan based on Regulatory Guice 7.10.

It is our understanding from your.. conversation of June 13, 1989 that the applicable sections of Annex 2 of the above Guide for the OSURR QA Program are as follows:

2.1 Organization 2.2 Q.A. Program (Scope) 2.4 Procurement Document Centrol 2.5 Instructions, Procedures, Drawings 2.10 Inspection Control 2.13 Handling, Storage, and Shipping 2.17 Q.A. Records 2.I8 Audits We are submitting it new with official approval from the University Reactor Operations Committee. After your review and subsecuent NRC accroval we recuest that we be red-*= red for a one year period to ship gg wet fuel to a DOE Facility using th nipping cask.

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@~4 If you have questions on this matter please cor. tact Mr. Richard Myser at 614/292-6755.

c, A SM yas. TRU Sincerely, eW W

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g Robert F. Redmond Director RFR/s Enclosure

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QUALATY ASSURANCE PROGRAN FOR THE OHIO STATE UNIVERSITY NUCLEAR REACTOR LABCRATORY Applicable to Procurement,'Use, Maintenance and Repair of Packaging Used in Transport of Rad'ioactive Materials introduction There are two reasons that a Quality Assurance (Q.A.) program be established.

First, The Ohio State University Research Reactor Safety Analysis Report (9.7 Quality Assurance) r$ quires the establishment and maintenance of a Q.A. program based on AJS-25.8 (Quality Assurance Program Requirements for Research Reactors).

It is to provide adequate confidence that safety-related items will perform satisfactorily in service.

Second, 10CFR71.22(B) requires a progran approved by the NRC that meets the requirements of Subparr H, Quality Assurance, for the Packaging and Transportation of Radioactive Materials.

It is the second of these that this program addresses.

It is based on Regulatory Guide 7.10 Annex 2.

Certain sections are not applicable at this time and are so marked.

Quality Assurance 4.s maintained by following good procedures.

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procedures are based on NRC Requirements. The OSURR Safety Analysis Report and Technical Specifications, and the CSU Off.ce of Radiation Safety Standards.

These procedures are reviewed and approved by the Reactor Operations Committee (ROC).

1.

Organication The rasponsibility for the Q.A. program is delegated to the Director of the NRL as shown in Figure I,

" Administrative Organization" His/her designee, normally the Associate Director, shall be responsible for the daily implementation of che program.

The Reactor Operations Committee has responsibility for independent raview and audit functions ascociated with the program.

The requf.rements for the allocation of Q. A. responsibilities are given in 10CFR71.103.

The responsibilities for the execution of the Q.A. Program are as follows:

A. NRL Director r

I. Establishes Facility's Q.A. policies, goals and objectives.

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Assures implementation of the recommendations contained in the ROC audits of the Q.A. Program.

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B. NRL Associate Director j

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1. Provides for Q.A. indoctrir.ation'and training of reactor I

staff.

I Independent]y reviews staff modification request packages to be submitted to Reactor Director for review if necessary.

2. Has overa]1 authority and responsibility for the implementation of the Q.A. program.

3. Maintains the Q.A. files.

4. Revjews designs, procedures, methods and checklists.

Refers these to the RCC for further study and approval

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when necessary.

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C. Reactor Operations Committee

3. Reviews Reactor Facility's Q.A. goals, objectives and

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policies.

Approves Q.A. Program and changes thereto.

Reviews modification packages consisting of, for examp}e: experiment designs; safety analyses; construction, installation and test plans; operating procedures and checklists.

2. Audits the Q.A. Program on an annual basis to assess its implementation. effectiveness and scope. This is to assure compliance with the 10CFR71.137 requirement of management independent periodic licensee r eview.

2.

Quality Assurance Program (Scone)

This Ohio State University Nuclear Reactor Laboratory Q.A. Program.

applies to the following:

Quality-affecting activities related to packaging: shipments of radioactive materials. This may include but is not limited to the packaging required fo'r the shipment of reactor fue[ -

elements.

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Design Control - Not Applicable i

4.

Procurement Document Control Procedures are established to ensure the'following:

A. The Q.A. program for the packaging is in hand and NRC approved.

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B. The verification activities required during use are in hand.

C. All pertinent documentation is furnished with the. packaging.

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5.

Instructions. Procedures. Trnwings Procedures are established to ensure the following:

A. Loading and unloading of radioactive material in and out of the packaging is controlled.

3 Surveys for contamination, radiation, pressure, rigging and others as necessary shall be completed.

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Document Control - Not Applicable 7.

Control of Purchased Material. Ecudament, and Services - Not applicable 8.

Identification and Control of Materials. Parts. and Components - Not applicable s

9.

Control of Scacial Processes - Not Applicable

10. Inspection Control Procedures are established for both receipt inspection of the packaging and final inspection before shipment.

These may be accomplished by the use of check lists.

II. Test Control - Not Applicable

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12. Control of Measuring and Test Eculomcnt - Not Applicable

13. Randlina, Storage. and Shinoine Proceditres are established that ensure the proper handling. lifting, and storage of the packaging.

In addition, procedures shall ensurg pre-shipment testing and NRC and DDT requirements including shipping papers are completed prior to shipment.

14. Inspection. Test. and Oneratine Status - Not Applicable

15. Control of Nor. conforming Materials. Parts.

or Comconents - Not Applicable

16. Corractive Action - Not Applicable

17. Quality Assurance Reccrds

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Radioactive Material shipping documents shall be maintained for a minimum period of two years after the date of shipment.

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18. Audits The Reactor Operations Committee conducts audits of the Q.A. Program

-on an annual frequency to determine its effectiveness, status, and y

adequacy.

The audit report is reviewed by the NRL Director who is responsible for the implementation of ROC recommendations.

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An audit of th shipment shall be done by audit procedure j

and/or audit checklist.

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UNITED STATES 3*

I NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 4

M JUN 2 6 892 SGTB: TOM 71-0680 The Ohio State University ATTN: Mr. Michael J. Davis 1298 Kinnear Road Columbus, OH 43212

Dear Mr. Davis:

s Enclosed is Quality Assurance Program Approval for Radioactive Material Packages No. 0680, Revision No. 1, as reinstated.

Please note the conditions in the approval.

We have also registered you as a user of Certificate of Compliance Number 5950 under the general license provisions of 10 CFR s71.12.

Sincerely, Charles t. MacDon[ld, Chief a

Transportation Branch Division of Safeguards and Transportation, NMSS

Enclosure:

As stated

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If QUALITY ASSURANCE PROGRAM APPROVAL 0680 CRC FO M 311 U. S. NUCLEAR f.EGULATO3Y COMMISSION

1. APPR OV A L NU MB E R,

(9-89) i FOR RADIOACTIVE MATERIAL PACKAGES E[SION NWBER i:

-"sji Pursuarrt to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974, as am-noed, and Title 10. Code of Federal E

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.gl Regulations. Chapter 1, Pan 71, and in reliance on statements and representations heretofore made in item $ by the person named in item 2, lp the Quality Assurance Program identified in item 5 is Pereby approved. This approval is issued to satisfy the reoverements of Section 71.101 lg.-

)p of 10 CFR Part 71. This approval is subject to all appiscable rules, regulations, and orders of the Nucleer Regulatory Commission now or g

li hereafter in eMect and to any conditions EDecified below.

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3. EXPIR ATION CATE The Ohio State University STREET ACCREss June 30, 1993 1298 Kinnear Road

4. 0cCx ET NuuseR CIT Y

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{ STATE l ZIP CODE Columbus i OH I43212 71-0680 f'

5. CUALITY ASSUR ANCE PROGR AM APDLICATICN DATEtS) n June 19, 1992

6. CON DITIONS l

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Activities authorized by this approval:use to be executed with regard to transp g[

procurement, maintenance, repair, and All other activities (i.e., design, fabrication, assembly, testing, and

'g; modification) shall be satisfied by obtaining certifications from package i

suppliers that these activities were conducted in accordance with an NRC-l approved QA program.

It shall remain the responsibility of the licensee-user j

that all transportation activities meet the requirements of 10 CFR s71.101.

2.

Records for each shipment of licensed material as required by 10 CFR s71.91(a)

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must be retained for a period of three years.

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