ML20210S605
ML20210S605 | |
Person / Time | |
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Site: | Dow Chemical Company |
Issue date: | 02/09/1987 |
From: | DOW CHEMICAL CO. |
To: | |
Shared Package | |
ML20210S595 | List: |
References | |
NUDOCS 8702170663 | |
Download: ML20210S605 (4) | |
Text
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DOW TRIGA RESEARCH REACTOR REQUALIFICATION PROGRAM 1987
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l 8702170663 870209 PDR ADOCK 05000264 PDR V
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- 1. GENERAL 1.1- The following program has been established for the periodic requalification of persons licensed to operate the Dow TRIGA Research Reactor. This program is intended to review topics and tasks important to the safe operation of the reactor, to review any changes which have been made in requirements and procedures, to evaluate the proficiency of the operators, and to provide for remedial training in case of deficiencies or weakness.
1.2. The reactor supervisor shall be responsible for the administration of this program.
1.3. The requalification program shall be conducted over a period not to exceed two years and shall be followed by successive two-year programs.
1.4. The program shall be divided into the following groups of topics for which preplanned training or preparation is scheduled:
a) Nuclear _ theory and principles of operation b) Design and operating characteristics l
O c) Instrumentation and control systems d) Safety systems e) Normal, abnormal, and emergency procedures f) Radiation control and safety g) Technical Specifications h) Administrative requirements 1.5. The Operating Manual and the license for the Dow TRIGA Research Reactor will provide the bases for these presentations.
1.6. 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.
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1.7. Each presentation shall be followed by a written examination.
1.8. The written examinations shall be.similar to the NRC written examinations for Reactor Operators and Senior Reactor Operators for this facility.
1.9. Results of the examinations shall be used to evaluate the proficiency of the operators.
- 2. EVALUATION, RECERTIFICATION, AND ADDITIONAL TRAINING
- 2.1 Additional training requirements in the form of formal l lectures, tutoring, self-study or on-the-job training shall be l based on the results of the examinations described above.
l l 2.2. An absolute score of at least 70% requires no additienal training.
2.3. An absolute score of less than 70% requires evaluation of the
, candidate's examination paper, past performance record, l supervisor's evaluation, and past test scores by the Reactor
! Supervisor or a designated Assistant Reacter Supervisor. A special oral examination may also be used to aid the evaluation. The reviewer (s) shall document the evaluation and fg 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 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 i 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, shutdowns, or significant reactivity changes during each year of the biennial requalification program. Direct supervision of these operations shall be considered equilivalent to actual performance for Senior Reactor Operators.
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3.2. -All licensed Reactor Operators and Senior Reactor Operators shall take part in a fuel inventory exercise, a control rod inspection, and a control rod calibration annually.
- 3.3. A systematic evaluation of the operating performance of certified individuals and any necessary retraining shall be performed and documented biennially 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 t.
, which may arise.
- 4. REVIEWS 4.1. All licensed Reactor Operators and Senior Reactor Operators shall review the emergency procedures at least annually.
4.2. All licensed Reactor Operators and Senior Reactor Operators 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 j fashion.
- 5. ABSENCE FROM AUTHORIZED ACTIVITIES 5.1. A licensed Reactor Operator or Senior Reactor Operator who has not actively performed licensed duties for a period in excess of 120 days shall demonstrate competence to perform such duties before being allowed to resume performance of these duties.
l 5.2. The demonstration shall be accomplished through interview or oral, written, or operational examination, or any combination
, of these.
l I 5.3. Remedial training shall be provided to correct any deficiencies
( uncovered through this demonstration.
l 5.4. This demonstration and any remedial training shall be i documented by the Reactor Supervisor.
- 6. RECORDS 1.
6.1. Records of the requalification program, including examinations, evaluations, and retraining shall be maintained as required by the license and my appropriate regulations.
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