ML20237L456

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Dow Triga Research Reactor Requalification Program
ML20237L456
Person / Time
Site: Dow Chemical Company
Issue date: 08/14/1987
From:
DOW CHEMICAL CO.
To:
Shared Package
ML20237L438 List:
References
NUDOCS 8708200226
Download: ML20237L456 (4)


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, i DOW TRIGA RESEARCH REACTOR REQUALIFICATION PROGRAM 14 AUGUST 1987 4

8708200226 870814 PDR ,\ DOCK 05000264 V PDR l

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l Rzqualification Program 14 August 1987 c 1

1. GENERAL ) ,

1.1 The following program has been. established for the periodic requalification of persons licensed to operate the Dow TRIGA l Research Reactor. This program is intended to review topics j and tasks important to the safe operation of the reactor, to '

review any changes which have been made in requirements and i procedures, to evaluate the proficiency of the operators, and to provide for remedial training in case of deficiencies or weakness.

i 1.2. The reactor supervisor shall be responsible for the i administration of this program. l 1.3. The requalification program shall be conducted over a period not to exceed two years and shall be followed by successive. l two-year programs.  ;

i 1.4. The program shall be divided into the following groups of topics for which preplanned training or preparation is scheduled:

i a) Nuclear theory and principles of operation

.i b) Design and operating' characteristics l c) Instrumentation and control systems d) Plant protection systems I e) Safety systems i f) Normal, abnormal, and emergency procedures g) Radiation control and safety h) Technical Specifications i

i) -Applicable portions of Title 10, Code of Federal l Regulations

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1.5. The Operating Manual and the license for the Dow TRIGA Research f Reactor will provide the bases for these presentations, j 1

1.8. The entire program covered by the topics in section 1.3. shall be completed over a two-year period, with topics generally being presented quarterly. J

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l Esqunlification Program 14 August 1987 (

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1.7. Each presentation shall be followed by a written examination. I 1.8. The written examinations shall be similar to the NRC written examinations for Reactor Operators and Senior Reactor Operators l for this facility.

1.9. Results of the examinations shall be used to evaluate the proficiency of the operators.

2. EVALUATION, DECERTIFICATION, AND ADDITIONAL TRAINING 2.1 Additional training requirements in the form of formal lectures, tutoring, self-study or on-the-job training shall be based on the results of the examinations described above.

2.2. An absolute score of at least 70% requires no additional training.

2.3. An absolute score of less than 70% requires evaluation of the candidate's examination paper, past performance record, supervisor's evaluation, and past test scores by the Reactor Supervisor or a designated Assistant Reactor Supervisor. A special oral examination may also be used to aid the evaluation. The reviewer (s) shs11 document the evaluation and shall determine whether the deficiencies are such as to require that the candidate's certification to operate the reactor should be withdrawn pending the successful completion of the l retraining program. The candidate shall not operate the reactor until after such an evaluation or the completion of a remedial training program, as required.

2.4. Training programs shall be administered to promptly correct any deficiencies, in any critical area that affects safety, which  ;

may be disclosed at any time.

3. REACTOR OPERATIONS 3.1. Each licensed Reactor Operator or Senior Reactor Operator at this facility shall perform at least ten reactivity manipulations in any combination of reactor startups, i shutdowns, or significant reactivity changes during each year of the biennial requalification program. Direct supervision of these operations shall be considered equivalent to actual performance for Senior Reactor Operators.

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l Rsqualification Program 14 August 1987 l

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l 3.2. All licensed Reactor Operators and Senior Reactor Operators i I shall take part in a fuel inventory exercise, a control rod ,

( inspection, and a control rod calibration annually. I I

f 3.3 Licensees shall actively perform licensed functions for a l minimum of four hours per calendar quarter.  !

3.4. A systematic evaluation of the operating performance of certified individuals and any necessary retraining shall be  !

performed and documented annually to ensure that they have the knowledge, competence, and dexterity to safely operate the reactor and to take proper action in response to any situations which may arise.

3.5. Each liennsee shall pass a comprehensive written  !

requalification examination. This written examination shall sample the items specified in 10 CFR 55.41 and 10 CFR 55.43.

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4. REVIEWS 4.1. All licensed Reactor Operators and Senior Reactor Operators )

shall rev.iew the emergency procedures at least annually.

4.2. All licensed Reactor Operators and Senior Reactor Operators i shall take part in an emergency exercise annually. '

4.3. All licensed Reactor Operators and Senior Reactor Operators shall be informed of changes in facility technical  !

specifications, design, and procedural changes in a timely fashion.

5. ABSENCE FROM AUTHORIZED ACTIVITIES 5.1. A licensed Reactc,r Operator or Senior Reactor Operator who has l not actively performed licensed duties for a minimum of four hours in any calendar quarter shall not perform licensed functions until an authorized representative of the facility licensee has certified that the qualifications and status of the licensee are current and valid and that the licensee has completed a minimum of six hours of licensed functions under the direction of a licensed Senior Reactor Operator. l l

5.2. Remedial training shall be provided to correct any deficiencies  !

uncovered through this demonstration.  !

5.3. This demonstration and any remedial training shall be documented by the Reactor Supervisor. l

6. RECORDS .

I 6.1. Records of the requalification program, including examinations, 1 evaluations, and retraining shall be maintained as required by  !

the license and any appropriate regulations.

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