ML20248A971
| ML20248A971 | |
| Person / Time | |
|---|---|
| Site: | 05000113 |
| Issue date: | 09/15/1989 |
| From: | ARIZONA, UNIV. OF, TUCSON, AZ |
| To: | |
| Shared Package | |
| ML20248A755 | List: |
| References | |
| NUDOCS 8910030059 | |
| Download: ML20248A971 (4) | |
Text
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OPERATOR AND SENIOR OPERATOR REQUALIFICATION PROGRAM FOR TIIE UNIVERSITY OF ARIZONA RESEARCII REACTOR Facility License R-52 Docket 50-113 Revision 1 September 15, 1989
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. . University of Arizona Operator Requalification Program s Page 1
- 1. GENERAL 1.1 The following program has been established for the periodic requalification of persons licensed to operate the TRIGA Research Reactor at the University of Arizona. 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 weaknesses.
1.2 The Reactor Supervisor shall be responsible for the administraiton of this prograin.
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 Each licensed RO and SRO shall pass an annual operating test that will demonstrate an understanding of, and the ability to perform, the actions necessary to accomplish a
, comprehensive sample of items specified in 10 CFR 55.45(a), (1) through (6) and (9) through l (13).
1.5 Each licensed RO and SRO shall pass a biennial comprehensive written requalification examination with an absolute score of 70% or greater. The RO written examination shall include a representative sample of items 10 CFR 55.41(b) (1), (2), (3), (5), (6), (7), (9), (10),
(11), (12), and (13). The SRO written examination shall include the items in 10 CFR 55.41 required for the RO written examination and shall include a representative sample of items 10 CFR 55.43 (b) (1) through (7).
1.6 The program shall include the following groups of topics for which preplanned lectures, training, or exercises shall be scheduled over a two-year period:
a) Nuclear theory and principles of operation b) Design and operating characteristics c) Instrumentation, control, and engineered safety systems d) Mormal operating procedures l
c) Emergency Procedures f) Radiation control and safety g) Protective action decision-making h) Technical Specifications i) Applicable portions of Title 10, Code of Federal Regulations 1.7 Each topic in Section 1.6 shall be followed by a written quiz covering selected parts of the material presented. '
Revision 1,9/15/89 t . - . . - . - _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _
. , University of Arizona Operator Regulification Program
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- 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 quizzes, examinations, and operating tests 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 operator's performance, past performance record, 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) shall document the evaluation and shall determine whether the deficiencies are such as to require that the operator's certification to operate the reactor be withdrawn pending the successful completion of the retraining program. The operator shall not operate the reactor until after such an evaluation or the completion of a remedial training program, as required.
2.4 If an operator is unable to attend a lecture, training session, or exercise, he shall pursue a program of study, reading, or exercises ar. proved by the Reactor Supervisor and take the quiz, or an equivalent quiz on the topic.
2.5 Training shall be administered promptly to correct deficiencies in any critical area that affects safety.
- 3. REACTOR OPERATIONS 3.1 Each licensed RO and SRO shall perform at least five reactivity manipulations in any combination of reactor startups, shutdowns, or significant reactivity changes, and five preliminary checklists during each year of the biennial requalification program. For an SRO, direct supervision of these operations shall be considered equivalent to actual performance.
3.2 Each licensed RO and SRO shall actively perform licensed functions for a minimum of four hours per calendar quarter.
3.3 Annually, each licensed RO and SRO shall perform or demonstrate verbally that he is capable of performing items 10 CFR 55.59 (c) (3) (i) (A), (E), (H), and (1) and biennially, he shall perform or demonstrate verbally that he is capable of performing items 10 CFR 55.59 (c) (3) (i) (R), (S), (U), (W), (Y), and (A A).
- 4. REVIEWS 4.1 Each licensed RO and SRO shall review the Administrative and Operating Procedures and tle Emergency Procedures at least once during the two year term of the program.
4.2 Each licensed RO and SRO shall take part in an emergency exercise annually. If en operator is unable to attend a scheduled exercise, he shall pass a quiz on the evaluation session following the exercise.
4.3 Each licensed RO and SRO shall be informed of changes in facility Technical Specifications, design, and operating and emergency procedures in a timely manner.
Revision 1, 9/15/89 1
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- 5. ABSENCE FROM AUTIIORIZED ACTIVITIES 5.1 A licensed RO or SRO who has not actively performed licensed duties for a minimum of four hours in any calendar quarter shall not perform licensed functions until either the Reactor Supervisor or the Reactor Laboratory Director has certifi?d 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 SRO.
- 6. RECORDS AND AUDIT 6.1 Records of the requalification program, including lecture materials, examinations, evaluations, as retraining shall be maintained as required by 10 CFR 55 and the facility.
6.2 The Requalification Program shall be reviewed by the Reactor Committee biennially.
Revision 1, 9/15/89