ML20247J969
| ML20247J969 | |
| Person / Time | |
|---|---|
| Site: | Ohio State University |
| Issue date: | 03/07/1989 |
| From: | OHIO STATE UNIV., COLUMBUS, OH |
| To: | |
| Shared Package | |
| ML20235Z339 | List: |
| References | |
| NUDOCS 8904050128 | |
| Download: ML20247J969 (6) | |
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n4 1 QUALITY ASSURAhtE PROGRAM l FOR THE OHIO STATE UNIVERSITY NUCLEAR REACTOR LABORATORY l
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) requires the establishment and maintenance of a Q.A. program based on ANS-15.8 (Quality Assurance Progrord Requirements for Research Reactors). It_is to provide adequate confidence that safety-related items will perform satisfactorily in service. Second, 10CFR71.12(B) requires a program approved by the NRC that meets the requirements of Subpart H, Quality Assurance, for the Packaging and Transportation of Radioactive Materials.
Quality Assurance is maintained by following good procedures. These procedures are based on NRC Requirements, The OSURR Safety Analysis Report and Technical Specifications, and the OSU Office of Radiation Safety
! Standards. These procedures are reviewed and approved by the Reactor l Operations Canmittee (ROC). ,
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l 1. Program Scope The Ohio State University Nuclear Reactor Laboratory Q. A. Pro rcus a
applies only to the following:
A. Replacement of or modification to reactor safety related systems such as
- 1. Fuel Elements
- 2. Control Rods and Drives !
- 3. Reactor Instrumentation
- 4. Cooling System .
- 5. Radiation Monitoring System {
i B. Design, construction, installation, and operation of experimental facilities. !
l C. Quality-affecting activities related to shipnents of f radioactive materials. 3 i
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President !
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'v} Provost Vice President for Health Services J
Dean, l College of Engineering l l
Reactor Operations !
Co:imi ttee 1
i s' Director, Engineering : j i
Experiment Station ;
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i 1 Director, .
Director, Nuclear Reactor j Office Radiation Safety Laboratory 1 I
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r b Associate Director, Reactor Users Nuclear Reactor Laboratory including NRL Staff i
l Senior Reactor Operator Reactor Operations Staff Solid Lines Paths of Direct Responsibility Dashed Lines ---------- Paths of Inf ormation Figure .1 ' Administrative Organization' l
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- 2. Program Organization)
The responsibility for the Q.A. program is delegated to the Director of the NRL as sine in Figure 1, " Administrative Organization".
His/her designee, normally the Associate Director, shall be responsible for the daily implementation of the program. The Reactor Operations Comtittee has responsibility for independent review and audit functions associated with the program. Reactor Users may include reactor staff, faculty, or students who perform experiments or plan changes that impact safety related items or ship radioactive materials.
The requirements for the allocation of Q A. responsibilities are given in 10CFR71.103. The responsibilities for the execution of the Q.A. Program are as follow:
A. Reactor Users
- 1. Develop system or experiment designs.
- 2. Perform safety or experiment review.
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O 3. Prepare procedures, methods and checklists.
( ) 4. Subnit designs, reviews, procedures, methods and checklists (modification packages) to the Associate Director for review.
- 5. Purchase and inspect construction materials.
- 6. Assenble or build systems or experimental facilities.
- 7. Install, test and operate systems or experimental facilities.
- 8. Prepare radioactive materials for shipnent.
- 9. Canplete procedures for the above and subnit these for approval and filing.
B. NRL Associate Director
- 1. Provides for Q.A. indoctrination and training of reactor staff.
- 2. Independently reviews staff modification packages to be subnitted to Reactor Director for review if necessary.
- 3. Has ovemil authority and responsibility for the implementation of the Q.A. program.
- 4. Maintains the Q.A. flies.
- 5. Reviem designs, procedures, methods and checklists, j Refers these to the ROC for further study and ]
approval when necessary.
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l C. NRL Director 'i 1.. Establishes Facility's Q.A. policies, goals and
, objectives.
- 2. Assures implementation of the reccmmvandations contained in the ROC audits of the QiA. Program, i .
D. Reactor Operations Ccanittee
- 1. Reviews Reactor Facility's Q.A. goals, objectives and' policies.
t 2. Approves Q. A. Pro, can and changes thereto. '
- 3. Reviews modification packages consisting of, for exadple: experiment designs; safety analyses; construction,. installation and test plans; operating procedures and checklists. (q ;
- 4. Audits the Q.A. Program on an annual basis to assess Jj its implementation, effectiveness and scope. This. ,
is to assure compliance with the 10CFR71.137 reGairementofmanagementindependentperiodic licensee review.
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- 3. Itdification Requests Written modification requests may be developed by experimenters, reactor staff, or health physics personnel, or combinations thereof.
These have m.a principal objective the evaluation of the reactor and radiological safety significance associated with proposed changes to reactor safety-related systems, or the introduction into 1 I
use of new reactor irradiation facilities. As necessary, probabilities and/or consequences of reactor accidents may be l considered in the detailed analyses, as related to safety margins .j
.and Technical Specifications.
Generally, the individual (s) initiating a reactor modification request will have it checked by the reactor staff or other experts.
The analysis should then be further reviewed by an SRO. ,
All analyses, together with other pertinent documentation such as drawings, material specifications, inspection procedures, calibration procedures, test plans, calculations, references to standards, etc..., as appropriate, will normally be assembled into a document package for sutmittal to the Associate Director. The Associate Director will determine whether sufficient documentation l 1s being presented and whether the experiment or system change involves an unreviewed reactor safety question. .
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f Materials to be used in the construction of reactor associated experiments, or in the modification of existing reactor safety-related systems, shall be chosen and checked for suitability and compatibility.
Failures, malfunctions or serious deficiencies of reactor safety ,
related itens, or reactor associated experiments, will be brought to the attention of the Reactor Director and the ROC. Corrective actions will be taken or initiated by the Reactor Director (or his designee), as appropriate.
- 4. Procedures Procedures, addressing the scope indicated in Section 1 of the'Q.A.
Plan, are prepared by the users in collaboration with/or by the ,
reactor staff, and approved by,the Reactor Operations Committee for routine use. Where pertinent, acceptance criteria should be indicated on the procedures. It is through the use of these procedures that the key operational aspects of the Q.A. program are carried out.
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('j When appropriate, Q.A. Procedures similar to the following examples will be canpleted:
- 1. OSURR Modification Requests (designed to meet 10CFR50.59 requirements).
- 2. Routine Shipnent of Radioactive Material.
- 3. Spent-fuel Shipping Procedure (to be developed).
The above typical procedures used in the implementation of the Q.A.
program are indicated as examples in the appendices to this document. Additional procedures may be developed, to spec'ifically meet special circumstances. Changes to existing procedures, or additional procedures, are not to be considered to be changes to the ROC and NRC approved Q.A. Program. Copies of new or revised procedures are sent to the ROC for review and approval.
- 5. Q.A. Training and Indoctrination The Associate Director will be the individual responsible for the training of reactor staff members in quality assurance matters.
Typically, training will be accomplished by junior staff getting hands-on directions from senior staff on why, when and how to canplete Q.A. procedures and by their participation in safety reviews and knalyses. The Q.A. program will also be a topic addressed in the reactor operator requalification lecture series.
) The Associate Director will assist users at the Reactor Facility
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with Q.A matters.
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- 6. Audits of Q.A. Program The Reactor Operations Committee will conduct audits of the Reactor Facility's Q.A. Program (10CFR71.137) on an annual frequency, to determine its effectiveness, status and adequacy. The audit report will be reviewed by the NRL Director, who will be responsible for having the ROC recommendations implemented.
- 7. Q. A. Records Documentation pertaining to the Q.A. Program will be kept by the Associate Director. tixilfication packages reviewed and approved by the Reactor Operations Comtittee should be kept in the ROC flies.
The retention period for Q.A. flies should be for the lifetime of the system described. Radioactive material shipping documents should be kept for a minimum period of two years after the date of shipnent.
Quality ass,.'rance documentation is not required to be on file for existing ass nilt facilities which predate the implementation of the original Q.A. program, k
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