ML20214C549

Dow Triga Research Reactor Requalification Program

ML20214C549
Person / Time
Site:	Dow Chemical Company
Issue date:	12/31/1986
From:	DOW CHEMICAL CO.
To:
Shared Package
ML20214C494	List: ML20214C492 ML20214C512 ML20214C535 ML20214C541 ML20214C549 ML20214C575
References
NUDOCS 8611210147
Download: ML20214C549 (3)

Text

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I DOW TRIGA RESEARCH REACTOR REQUALIFICATION PROGRAM 1986 I

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I 8611210147 861114 PDR P

ADOCK 05000264 PDR I

I I l I All licensed reactor operators and senior reactor operators of the Dow TRIGA Research Reactor shall participate within each calendar year in l

I a Reactor Operator Requalification Program consisting of the following parts:

A. A series of lectures following closely the material covered in the up-to-date version of the Instruction Manual for the Dow TRIGA Research Reactor facility on the following subjects:

I 1. Physical layout of the facility and specific operating characteristics, and changes of tha facility during the preceding 12 months.

2. Reactor instrumentation, control and safety systems.

3. Administrative procedures; Plant Protection systems;

'I emergency procedures, technical specifications, changes in the techn!. cal specifications during the previous 12 months.

4. Operating procedures, normal, abnormal and emergency.

Changes in operating procedures which became effective during the previous 12 months.

5. Radiological safety; 10 CFR 20 and other items of Title 10.

6. Reactor physics, theory.

The lectures shall be given by one or more persons holding senior reactor operator licenses for the facility or have similar qualifications for the subject they are covering.

5 B. A 1 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ' walk through the facility" with discussion led by the reactor supervisor.

C. A simulated emergency situation with evacuation exercise.

D. The above parts of the program shall be followed by a

! written examination containing at least 12 questions which .

can be answered in approximately two hours and will demonstrate the familiarity of the operator with the subjects covered.

l E. All operators shall participate in the yearly check of the facility: the annual fuel inspection, the inspection and recalibration of the control elements.

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I F. Each operator shall attend at least one of the quarterly meetings of the Reactor Operations Committee within each calendar year.

G. Each licensed operator shall operate the reactor at least once every 120 days and shall perform a minimum of ten reactivity changes during each calendar year.

The results of the requalification program shall be evaluated by the reactor supervisor and his designated alternate. Appropriate records including the scored written examination, documentation of requirement (g) above, etc., for each operator shall be kept by the f acility.

Operators who were unable to abtain a passing grade in the written examination [ Item (D) above] shall be offered an accelerated review / training program set up to meet the individual's need by the I reactor supervisor. This remedial program will be concluded by a two hour oral examination in the form of a walk through the facility administered by the reactor supervisor and a second licensed senior reactor operator of the facililty. Reports on the type of remedial program given and the evaluations made during the oral examination shall be kept in the individual's file at the facility.

I Licensed operators who have not been able to meet Item (G) above will be given a brief updating course by the reactor supervisor which shall include a two hour walk through the facility, a review of the state of the facility including recent changes in design, instrumentation, operating procedures, technical specifications, and other items pertaining to the facility and its operation. Satisfactory completion of the update including a certification of the readiness of the operator to resume his duties shall be documented by the reactor supervisor and the certification document shall be placed in the operator's file in the facility prior to resumption of reactor operation by the individual.

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