ML20211G964

Rev 2 to Administrative Procedure AP-09, Reactor Operator/ Senior Reactor Operator Requalification

ML20211G964
Person / Time
Site:	Ohio State University
Issue date:	10/27/1986
From:	OHIO STATE UNIV., COLUMBUS, OH
To:
Shared Package
ML20211G950	List: ML20211G947 ML20211G964
References
AP-09, AP-9, NUDOCS 8611040342
Download: ML20211G964 (7)

Text

e w Administrative Procedure 'AP-09 RO/SRO Requalification I. SCOPE:

This instruction outlines the requirements.for.requali-f ying RO's and SRO's at the OSU-NRL.

II. DISCUSSION:

.The RO/SRO requalification program is designed to demon-strate RO/SRO competence and to satisfy the requirements of 10CFR55.33(c)(2) and 10CFR55_ Appendix A. For the purpose of this procedure RO shall refer.to any licensed Reactor Operato'r, SRO shal l refer to any licensed Senior Reactor Operator, and Operator shall refer to any li-censed operator, reactor, or senior reactor.

III.

REFERENCES:

A. 10CFR55.33(c)(2)

~8. 10CFR55 Appendix A C. AP-07 Review of Procedures

.D.'AP-10 OSURR Console Operating Experience E. ANS I / ANS- 15.4 - 19 7 7 Selection and Training of Personnel for Research Reactors.

F. NRC Generic Letter No. 84-06 Operator and. Senior

Operator License Examination for Passing Grade (To

! All Non-Power Reactor Licensees) j IV. PRECAUTIONS:

1 i To maintain an active Ope ra tor 's License at the OSU-NRL one shal l:

A. Be the console operator at least once every four i

months and a total of at least 10 times per bien-nium.

8. Complete the OSU-NRL Annual Requal Exam success-f u l l y and in a timel y manner.

C. Renew on e 's NRC License every two years in a

! timely manner.

l 8611040342 861027

-PDR ADOCK 05000150 V PDR RDM 27 MAR 86 REV. 2 AP-09 1 5

s. ..

V. PROCEDURE

S:-

Al INTRODUCTION.

1The Operator Requalification Program is designed to demonstrate Op'erator and Senior Operatorfcompetence,.

and to. satisfy the requirements of 10CFR55.33(c)(2) for. license renewal. The Program embodies the sub-stance of 10CFR55 Append 1x A, including provisions

.for an annual written' examination, a structured lec-ture'and study program,.on_the. Job training and Levaluation of l icensees, and a records maintenance-system.

During.each calendar ~ year, a comprehensive written -

exam ina tion ' s ha l l be administered to all licensed

, personnel having regular operational responsibility at'The' Ohio State University Nuclear' Reactor Labora-

. tor'y (NRL). This ~ exam shal l be of a compl exi ty.

equivalent to the examination given at this facility.

by the examiners from the NRC.

Subsequent to determining any deficiencies indicated.

by the comprehensive-examination, a retraining pro-gram will be initiated which consists of a combina-tion of pre-planned lectures, sel f-study. by the li-censee,= tutoring of the licensee, and appropriate-examination on the' material covered. The final se-lection of the combination of retraining sessions, will depend upon the performance of'the licensee on the writter examination.

All study materials used in -the Program shal l be're-viewed to assure they remain current. Study mate--

rials shall be collected and made available to.all licensees throughout the year.

B. PROGRAM ADMINISTRATION AND REVIEW The Associate Director of the NRL shall serve as the Training Coordinator, and shal l be responsible for the-implementation, coordination, and operation of the Operator Requalification Program. He will pre-pare, administer, grade, and review al l examinations and quizzes' required"by the. Program. In this capaci-ty, and.since he is- a licensed Senior Operator, he will be considered as having completed the examina-tions and retraining program requirements.

C. COMPREHENSIVE ANNUAL WRITTEN EXAMINATION

1. The comprehensive annual written examination (Exam) given to all licensed personnel., will in-clude questions taken from:

REV. 2 AP-09 2 5

c --

ce e 1 A. Principles of Reactor Operation

8. Features of Facility Design C. General Operating Characteristics D. Instruments and Controls E. Safety and Emergency Systems F. Standard and Emergency Operating Procedures G. Radiation Control and Safety H. Reactor Theory I. Radioactive Materials Handling, Disposal and Hazards J. Specific Operating Characteristics K. Fuel Handling and Core Parameters L. Administrative Procedures, Conditions, and Limitations.

2. The Exam for Reactor Operator licensees shall be on topics A through G. The Exam for Senior Reac-tor Operator licensees shal l consist of questions taken f rom topics 8, D, E, F, and H through L.

3. The Exams wil l be graded, reviewed and retained at the NRL. For each l icensee, a review f orm wil l be prepared indicating his grade in each Exam cate-gory. The areas of deficiency and the retraining to be followed in improving the l icensee's compe-tence in that area will then be determined. A grade below 55% in a single category shall require retraining for that licensee in that area of de-ficiency. An overall score below 70% on the Exam shall require that:

A. Prior to continuing his responsibilities of operation of the OSURR, the l icensee- sha l l be given an oral exam to verify competence as a console operator, and

8. The licensee shal l be immediately enrol led in a retraining program.

D. RETRAINING PROGRAM

1. The Retraining Program shall consist of an appro-priate series of REV. 2 AP-09 3 5

a. Pre-planned lecturcs,

b. Self-study of reference materials, and

c. Tutoring sessions, as may be indicated to correct deficiencies noted during review of the written Exams. Quizzes will be given during the retraining period on the to-pics being covered. These quizzes shal l meet the general criteria outlined for the Comprehensive Annual Written Examinations, as indicated pre-viously, and will be graded and included in the l icensee's file. In cases requiring retraining, a program will be organized,-implemented, and con-ducted within a period of 90 days.

E., REACTOR OPERATION One reactor operation of each year for each licensee shal l .be devoted to operator requa l i f ica t ion. The Training Coordinator shall be present in the control room during al l reactivity control manipulations as-sociated with the operation, and shall evaluate the O pe r a t o r 's performance, competence, knowledge of the reactor system, and knowledge of operating and emer-gency procedurec.

A quarterly review shall be performed to assure that each licensee has participated in at least one reac-tor operation during each four month period and ten operations every two years.

F. RETRAINING STUDY MATERIALS-A compl ete set of study and ref erence materials shal l be provided f or use by the licensees. It sha l l be the responsibility of the Training Coordinator to perform an annual review of the contents of these reference materials to ensure they are adequate and accurately reflect operations, conditions, and design characteristics of the facility. As a minimum, these materials shal l include:

1. A suitable general reference text on reactor phy-sics

2. Copies of the operating procedures for the NRL

3. Copies of the Technical Specifications for the OSURR

4. Copies of emergency procedures for the facility

5. Copies of the Reactor Description and Hazards Sum-mary Report REV. 2 AP-09 4 5

a .

. 6. Copies of 10CFR2 0, 50, and 55

7. Reference material on Heal th Physics principles and techniques.

G. SPECIAL CONDITIONS

1. A licensee who does -not participate in reactor operation for four or more months, shall be given an oral examination on facility and procedure changes, and shall perform a reactivity manipula-tion under the observation of a Senior Operator before being reassigned regular operational duties at the f acility, provided he is up to date on the comprehensive annual written examination. The results of the oral and performance examination

, provide the basis for recertification of compe-tence to the NRC, as required by 10 C F R 5 5. 31 (e ) .

Resul ts of these examinations shall be retained in the l i c ens ee 's file.

2. Successful completion of the initial NRC licensing examination shal l be considered to satisfy the l i c en s ee 's annual retraining requirements. Such an individual's retraining program should be star-ted with the next Exam schedu l ed at least 6 months after the l i c en s ee 's initial licensing date.

3. A licensee who does not compl ete the annual exam in a timely manner shal l not be a l lowed to operate until the exam is successfully completed and graded.

H. RECORDS These records sha ll be retained at the NRL f or a period of five years:

1 All Exams, quizzes, and required re-examinations, which were taken by the l icensee during each of the requalification periods

2. The examination review sheets fil led out at the conclusion of the Exam and after any indicated re-exams

3. Summaries of control manipulations for licensees involved in the requalification program (See AP-10) 4 Certification that each licensee has reviewed changes in the facility license, design, and procedures. (See AP-07)

VI. ATTACHMENTS:

A. Exam Summary Sheets REV. 2 AP-09 5 5

o. .

THE OHIO STATE UNIVERSITY RESEARCH REACTOR REACTOR OPERATOR ANNUAL COMPREHENSIVE REQUALIFICATION EXA"INATION DATE PRINT NAME

~

Read each question carefully. If a question seems ambiguous, define your interpretation and list any assumptions you must make.

Show all steps leading to a concluding answer to obtain partial credit. Use lined white paper for your answer sheets.

TOTAL  % OF CATEGORY TOTAL RO'S  % OF CATEGORY POINTS (8Y PARTS) SCORE CAT. PTS.

PART I A. Principles of Reactor Operation 10.0 14.3 _______ _______

8. Features of Facility Design 10.0 14.3 _______ _______. (

1 C. General Operating Characteristics 10.0 14.3 _______ _______

D. Instruments and Controls 10.0' 14.3 _______ _______

E. Safety and Emergency Systems 10.0 14.3 ._______ _______

F. Standard and Emergency Operating Procedures 10.0 14.3 _______ _______

G. Radiation Control and Safety 10.0 14.3 _______ _______

Total 70.0 100.0 _______ _______

G

ae. .

THE OHIO STATE UNIVERSITY RESEARCH REACTOR

,..SE.4IOR REACTOR OPERATOR ANNUAL COMPREHENSIVE REQUALIFICATION EXAM

-_--------_------_-___---_--_---_-------u---------------_---_-----

__-_____-____ i 1

UATE PRINT NAME l Read each question careful ly. If a question seems ambiguous, define your interpretation and list any assumptions you must make.

Show all steps leading to a concluding answer to obtain partial credit. Use lined white paper for your answer sheets.

TOTAL  % OF CATEGORY TOTAL SRO'S  % OF CATEGORY POINTS (8Y PARTS) SCORE CAT. PTS.

PART I

8. Features of Facility Design 10.0 11.1 ______ ______

D. Instruments and Controls 10.0 11.1 ______ ______

E. Safety and Emergency Systems 10.0 11 1 ______ ______

F. Standard and Emergency Operating Procedures 10.0 11.1 ______ ______

PART II H. Reactor Theory 10.0 11.1 _______ _______

I. Radioactive Materials Hand-ling, Disposal, and Hazards 10.0 11.1 _______ _______

J. Specific Operating Characteristics 10.0 11.1 _______ _______

K. Fuel Handling and Core Parameters 10.0 11.1 _______ _______

L.' Administrative Procedures, Conditions, and Limitations 10.0 11.1 _______ _______

Total 90.0 100.0 _______ _______