ML20150C876

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Requalification Program for Licensed Operators of Oregon State Univ Triga Reactor (Ostr)
ML20150C876
Person / Time
Site: Oregon State University
Issue date: 03/15/1988
From:
Oregon State University, CORVALLIS, OR
To:
Shared Package
ML20150C830 List:
References
NUDOCS 8803220369
Download: ML20150C876 (6)
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REQUALIFICATION PROGRAM FOR LICENSED OPERATORS OF THE OREGON STATE UNIVERSITY TRIGA REACTOR ")STR) 8803220369 880315 PDR ADOCK 05000243 V DCD

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REQUALIFICATION PROGRAM FOR LICENSED OPERATORS OF THE OREGON STATE UNIVERSITY TRIGA REACTOR (OSTR)

1. Introduction (a) This reactor operator requalification program is designed to satisfy the requirements of the USNRC's rules contained in 10 CFR 55, particularly those in 10 CFR 55.59. It also generally complies with the requalification program in ANS-15.4; Standard for Selection and Training of Personnel for Research 'teactors.

(b) This requalification program supercedes all previous OSTR programs for operator requalification, and shall be put into effect upon approval by the USNRC.

2. Administration (a) The responsibility for the requalification program will lie with the Reactor Supervisor. This responsibility will cover the following items:

(i) Selection of knowledgeable individuals to give classroom lectures and to supervise retraining operations.

(ii) Certification to the Reactor Administrator that each individual has successfully completed the requalification program.

(iii) Granting of exemptions to the requalification program as provided for in Section 6 (c) of this plan.

3. Schedule (a) The requalification program will be conducted on a cycle not to exceed two years. Upon conclusion, it will be promptly repeated.
4. Content (a) The requalification program will consist of preplanned lectures, written examinations, an annual operating test, and routine reactor operation.
5. Lectures (a) Each year a series of lectures will be given which cover approx-imately one-half of the subjects listed in 10 CFR 55.59(c)(2).

(b) The topics selected will be such that all of the subjects will be covered at least once during the two year cycle of the re-qualification program.

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(c) Procedures for abnormal and emergency situations will be reviewed annually to meet the requirements of 10 CFR 55.59(c)(3)(iv).

6. Examinations (a) Written examinations will be given covering the lecture material.

(b) The individual giving the lecture on a particular subject will formulate, administer, and grade the written examination on that subject.

(c) Any licensed individual pr2 paring and grading an examination is exempt from taking that examination.

(d) All written examinations will be proctored by the individual administrating the exam, or by his appointed representative.

Under no circumstances ~can the proctor be an individual taking the examination.

(e) The written examinations, along with the annual operating test described in Section 7, are deemed appropriate to fully meet the requirements of 10 CFR 55.59(a)(2) and (c)(4)(i)&(ii).

(f) In accordance with 10 CFR 55.59(4)(v), provisions for a licensed individual to participate in an accelerated requalification program will be made when there is a need, as indicated by the performance evaluations (i.e., the written examinations and the annual operating test).

(g) Until such time as a person performs satisfactorily in the written examinations and operating test, the individual will not be allowed to continue licensed duties.

7. Annual Reactor Operating Test, Observation, and On-The-Job Training (a) A reactor operating test will be performed annually, but at intervals not to exceed 15 months.

(b) During the operating test the licensed individual will be observed and evaluated by the Reactor Supervisor. The operational competency of the Reactor Supervisor will be assessed by another senior reactor operator.

(c) The operating test will require the reactor operator or senior reactor operator to demonstrate an understanding of and the ability to perfor.n a comprehensive sample of the applicable tasks in 10 CFR 55.45(a)(1) through (13).

(d) The operating test will include an actual or simulated response to an abnormal, emergency situation. This aspect of the test is deemed appropriate to fully meet the requirements of 10 CFR 55.59(4)(111) and (iv).

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e (e) The manipulations required during the annual operating test will be such that they will also meet the requirements of the applicable parts of the on-the-job training specified in 10 CFR 55.59(c)(3)(1)

(A) through (AA), and the evaluation of reactor manipulations stated in 10 CFR 55.59(c)(3)(ii).

8. Facility Design Changes, Procedure Changes, and Facility License Changes (a) As required by 10 CFR 55.59(c)(3)(iii), each licensed reactor operator and senior reactor operator will be kept informed of all facility design changes, procedure changes, and facility license changes. This will be achieved by use of the procedure and bulletins described in OSTR Operating Procedure (OSTROP) 6.0.
9. Reactor Operation and Active License Status (a) To maintain an active license, all licensed reactor operators and senior reactor operators must perform an operating exercise each calendar quarter. This exercise will, as a minimum, consist of a reactor startup, an increase to power and a shutdown, and will be supervised, evaluated, and verified by the Reactor Supervisor.

The operating exercise for the Reactor Supervisor will be evaluated and verified by another senior reactor operator.

(b) In addition to 9(a) above, a reactor operator must operate the reactor for a minimum of four hours per calendar quarter.

(c) In addition to 9(a) above, a senior reactor operator must perform the duties of the Reactor Supervisor for a minimum of four hours per calendar quarter. Such duties may include actual operation of the reactor.

(d) If a licensed reactor operator or senior reactor operator has not met the applicable requirements for maintaining an active license status as stated in 9(a),(b), and (c), then before resumption of licensed duties, the operator or senior operator shall:

(1) Satisfactorily perform the annual operating test.

(ii) Operate the reactor for a minimum of six hours under the direction of an actively licensed reactor operator or senior reactor operator, as appropriate, depending upon the license held by the individual undergoing license reactivation..

10. Certification of Competency (a) At the conclusion of the annual reactor operator requalification program or in cases where an inactive license is being reinstated to an active status, and in consideration of certifications received from the Reactor Supervisor, the Reactor Administrator shall certify to the Reector Operations Committee (ROC) that the qualifications and status of each licensed operator is current and valid.

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(b) Upon approval by the ROC,lthe operator (s) or senior operator (s)'

may then resume licensed duties.

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11. Records-(a)' All records pertaining to the requalification program shall. be maintainedaccordingto10CFR65.59(c)(5).

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' Operator Examiner Date AlgEIAL OPERATING TEST (Also meets on-the-job training requirweent)

Completed Successfully Test Items 10 CFR 55.45 ref. 10 CFR 55.59(c)(3) ref.

1. Rx startup (2),(6)(12),(13) [A]
2. Core excess measurwnt (2),(6),(12),(13) [A]
3. Increase power to 1 MW (auto or manual (2),(6),(8).(12),(13)- [A]
4. Change power level ?_10% in manual (2),(6),(12),(13) [A.E]
5. Record a set of instrument readings (4),(5),(9)(12).(13) ,
6. Respond to any annunciators (3),(6),(12),(13) }
7. State responses, or respond to.

1 all of the following abnormal I situations (at least one of which mustbesimulated): (6).(8),(11).(12),(13) '

a) Loss of coolant [GJ]

b) Loss of electrical power [1]

c) Loss of safety, percent power, '

period, log /lin, temperature channel [Q,AA] -

d) Rod drop [R]

e) Inability to drive rods [5] ,

f) Fuel cladding failure (9),(10) [U)  ;

e g) High CAM or Stack Effluent alarm (9),(10) [U]

h) Malfunction of auto or square 1

wave system [W) ,

8. Shut down the reactor [B.Y]

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