ML20067B582

Requalification Program for Univ of Ok

ML20067B582
Person / Time
Site:	05000112
Issue date:	10/11/1982
From:	OKLAHOMA, UNIV. OF, NORMAN, OK
To:
Shared Package
ML20067B561	List: ML20067B572 ML20067B582
References
NUDOCS 8212060233
Download: ML20067B582 (6)

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,i REQUALIFICATION PROGRAM FOR UNIVERSITY OF OKLAH0MA AGN-211P REACTOR

! LICENSE R-53

! DOCKET 50-112 i

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I Editorial and clarification revisions made 10-11-82 4

I 8212060233 821201 PDR ADOCK 05000112

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I REQUALIFICATION PROGRAM University of Oklahoma AGN-211P Reactor (I) INTRODUCTION The purpose of the requalification program is to ensure that reactor operators (RO) and senior reactor operators (SR0) maintain their competence in the manipulation and operation of the University of Oklahoma's reactor.

Implementation of the program is through a series of meetings in which all licensed members of the reactor staff (director, supervisor, SR0's, R0's and persons in training as R0's) are required to participate and take annual examinations. The requalification program meetings will consist of discussions on subjects related to safe reactor operations, reviews of I procedures, technical specifications, emergency plans, federal and state regulations and other matters relative to the safe operation of the reactor.

The reactor director and the reactor supervisor will be responsible for the conduct of the program.

(II) PROGRAM SCHEDULE The foundation of the program is based on a series of REVIEWS and Annual Examinations.

A. Reviews The purpose of the Reviews is to cover a subject (such as emergency procedures) thoroughly at least once a year. The subject may be covered by a lecture presented by a member of the reactor staff or by a reading and discussion of the subject or a procedure related to the subject.

A review meeting will normally be scheduled for a one to two hour 3

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period. A series of six formal Review meetings will be held annually during the September to May academic year, since all personnel are not necessarily present in the summer.

The subjects of the six meetings are as follows:

1. Reactor Operations and Procedures and Regulations The following will be reviewed at a minimum;

a. sample irradiation and experiment form

b. reactor checkout and shutdown precedures

c. reactor characteristics (rod worth, excess, temperaturecoefficient,radiationlevels,etc.)

d. core fuel configuration and fuel handling procedures

e. visitor regulations

f. student regulations 9 researcher regulations

h. reactor room security (both day and night)

1. experimental procedures J. radiation monitoring procedures

k. Other related procedures

2. Emergency Plan The emergency plan will be reviewed and discussed.

Hypothetical situations will be postulated and the appropriate response determined as defined by the emergency plan.

The following additional personnel will be requested to l participate in this review:

Radiation Safety Officer or his designate, i

l Representatives from the Reactor Safety Committee, Representative from the Fire and Safety Division of l the OU Police Department.

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3. Technical Specifications The technical specifications will be read and discussed to ensure that all personnel are familiar with the details. Where a calculation is required, such as for excess reactivity, a sample calculation will be done.

A complete review of all applicable Federal, State and University regulations which affect the reactor's operation will be done.

4. Maintenance and Calibration Procedures The purpose of this Review is to cover maintenance and calibration procedures which are required.

5. Theory of Reactor Operations l The purpose of this review is to ensure that all personnel stay informed on reactor theory which is related to operation i

of the OU reactor. Subjects covered will include, criticality, reactivity, activation, control rod worth, importance, neutron flux and any other subjects requested by the staff. This discussion will be given by the Reactor Director or where appropriated by members of the Nuclear Engineering Faculty.

6. Other Subjects l

Subjects to be selected by the Reactor Director, Reactor Supervisor or requested by the operations staff or suggested by the Reactor Safety Committee or the Radiation Safety Officer.

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B. Annual Examinations Both written and operating exams will be given to all members of the reactor staff (all who hold operators licenses) annually.

The written exam will be prepared and graded by a member of the Reactor Safety Committee, a member of the Nuclear Engineering Faculty, or by the Reactor Director, as is appropriate. A score of 70 is considered to be a minimum passing grade. Three hours will be alloted to complete the written exam which is a closed book test.

The written exam will normally consist of four sections:

1. Theory of Operations Relative to the OU Reactor

2. Reactor Characteristics (Physical and Operating)

3. Procedures and Regulations

4. Radiation Safety The operating exam will consist of a complete checkout of the reactor, arrangement of the fuel in the standard or the flux trap configurations, operation at several power levels, excess reactivity determination, simulation of emergency or abnormal cor.ditions and shutdown. In general, the Reactor Supervisor will conduct the practical exam and grade the performance on a pass / fail basis.

In the event a grade of less than 70% is achieved on the written exam, the R0 or SRO will undertake an iInmediate study-review program relating to areas of weakness. Within 60 days a second written exam will be given. Failure to achieve a grade of 70% on this second exam will result in an immediate suspension of operator status. The future of such an operator will be considered by the Reactor Director and the Reactor Safety Committee.

Failure to achieve a grade of pass on the practical exam will result in one or more training sessions conducted by the Reactor 4

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Supervisor. A second exam will be administered within 60 days.

Failure to achieve a passing grade will result in an immediate suspension of the individual's operator status. The future of such an operator will be considered by the Reactor Director and the Reactor Safety Committee.

(III) RECORDS The following records relative to the requalification program will be maintained by the Reactor Supervisor:

(A) This document (B) Outline of all Review meetings (C) Administered written annual exams and record of the operating test (D) Results and evaluations of graded exams (E) Recommendations to the individuals who have taken the exams (F) Any other material pertinent to the implementation of this program.

It is noted that the Requalification Program is a requirement of the Reactor's operating license. Changes in this program must have the approval of the Reactor Safety Committee and must be forwarded to the NRC for their concurrence before any changes may be implemented.

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