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l REQUALIFICATION PROGRAM FOR ItEACTOR OPERATORS / SENIOR REACTOR OPERATORS GEORGTA TECil RESRARCII REACTOR January 2, 1991 Docket No. 50-160 License No. R-97 l
9012260068 901221 PDH  ADOCK 05000160
                'V                PDR
 
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GTRR OPERATOR / SENIOR OPERATOR REQUALIFICATION PROGRAM 1.0  PURPOSE To establish the procedures and criteria to be used in the conduct of operator / senior operator train.ing and requalification for the Georgia Tech Research iluactor (GTRR).
2.0  SCOPE 2.)  Extent of Training 2.1.1 Training to be provided shall include classroom lectures and on-the-job training which shall be suf ficientl-thorough and detailed to ensure the maintenance of a hig-level of competence by the Reactor Operators (ROs)/ Senior Reactor Operators (SROs).
2.1.2 Topics that will be covered in formal classroom training are presented in Section 4 and the listing of reactor control manipulations that shall be required of each RO/SRO in the Requalification program are specified in Section 5.
,          2.1.3 The' activities described in the Requalification Program L                shall also constitute the requirements-for the initial training of an unlicensed individual.          Successful completion of the requalification program should enable a candidate to successfully complete the Reactor Operator examination given by the U. S. Nuclear Regulatory Commission.
2.2:  Testing and Evaluation i                Evaluation of. the adequacy of the Requalification Training program shall be ensured through the mechanism of formal, written tests as well as evaluation of hands-on performance of the ROs/SROs.                              '
2.3  Documentation l
Each aspect of the requalification training for ROs/SROs shall be documented through the creation of records which shall be maintained at the Neely Nuclear Research Center.
Examples of the forms that shall be utilized in the i
 
3 documentation              are attached                                                                to the  Requalification Program.
3.0                                QENERAL REOUIREMENTS 3.1                                Licensing of ROs/SROs for the GTRR is performed by the United States Nuclear Regulatory Commission ' 'JSNRC ) .
Each license is issued for a period of six ye s .
                                                              .2                              The  Requalification Program for ROs/SROs shall be conducted by Georgia Tech or its designee, af ter approval of the program by the USNRC.
3.2.1                              The frequency of the roqualification shall be a two year cycle, 1. e., at the end of two years, each RO or SRO shall have successfully completed each portion of the Requalification Program as evidenced by successful completion of a comprehensive, written examination and required on-the-job performance evaluation.
3.2.2                              Successful completion of the Requalification Program shall be demonstrated by a passing grade of 70.
3.2.3                              The requalification examination shall be comprehensive in that it shall include the major topics identified in Section 4.
3.2.4                              During the conduct of the Requalification Program, an examination shall be given at the completion of each series of lectures.
3.2.5                              As part of the Requalification Program, ROs and SROs shall be required to successfully complete a reactor controls manipulation evaluation.                                                                            Certification of completion shall be provided by the Manager of Operations or his/her designee.
4.O                                  CLASSROOM TRAINING 4.1                                A series of lectures covering seven subjects shall be provided for the Requalification applicant during each requalification interval of two years.                                                                        A listing of the seven subjects is provided below.
4.1.1                              Reactor Theory and Principles of Operation 4.1.1.1                            Material covered will include elementary nuclear reactor theory, technical terminology, basic heat transfer and the processes that occur in a nuclear reactor.                                                                          These process include controlled and variable parameters of the
 
4 reactor, primary and secondary coolant systems and auxiliary systms. Hoactor transients, both nantal and off-normal will also be included.
4.1.1.2      A successful candidate must possess mathematical skills that  allow him/her      to  determine    exponential                                and logarithmic functions.
4.1.1.3      The duration of the _        sroom lactures and examination for this subject will be approximately 15 hours.
4.1.2        General and Specific Plant Operating Characteristics 4.1.2.1      The process variables and physical properties of the reactor during normal operating conditions describe the specific operating characteristics of a reactor.                                    These shall be covered      for the GTRR and          shall be drawn primarily from the Safety Analysis Report                                          (SAR),
Technical Specifications (TS), completed experiment irradiations, the console log book, operating procedures and the operating experience of the reactor staff.
4.1.2.2      The duration of the classroom lectures and examination for this subject will be approximately 3 hours.
4.1.3        Reactor Instrumentation and Control Systems, Reactor Protection Systems and Engineered Safety Systems 4.1.3.1      Lectures  will ' include- the    material                listed                  below.
Generally, the primary sources of material for these lectures will be drawn from the SAR, TS and GTRR drawings.
4.1.3.1.1 Radiation Detectors 4.1.3.1.2 Nuclear Instrumentation 4.1.3.1.3 Procees Instrumentation 4.1.3.1.4 Reactor Control Circuits 4.1.3.1.5 Reactor Safety Circuits 4.1.3.1.6 Scram Parameters and Set Points 4.1.3.1.7 Emergency Core Coolant System 4.1.3.1.8 Annunciator Parameters 4.1.3.1.9 Interlocks and Permissives
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4.1.3.2  The duration of-the classroom lectures and examination for this subject will be approximately 5 hours.            j 4.1.4-    Normal, Off-Normal and Emergency Operating Procedures 4.1.4.1  Written, approved procedures shall be used for reactor      l operations.                                                l l
4.1.4.2  Each RO, SRO or candidate for an operator position shall-  l be provided with an up-to-date copy of the Procedures      I Manual.                                                    )
I t:              4.1.4.2.1 Normal Operations shall be covered in the series of l-J procedures numbering 2xxx.
4.1.4.2.2 Auxiliary Systems _ procedures shall be covered in the ceries of procedures numbering 3xxx.
4.1.4.2.3 Site Emergency Procedures shall be covered in the series of procedures numbering-6xxx.
4.1.4.3  The duration of the classroom lectures and examination for this-subject will be approximately 5 hours.
4.1.5    Technical Specifications 4.1.5.1  The GTRR Technical Specifications,- which have been approved by the USNRC, will'be the primary source of material for this subject area.
              ' 4.1.5.2  The duration of.the classroom lectures and examination for this subject will be approximately 5 hours.
l L              - 4'1.6
                  .      Radiation Control and Safety-4.1.6.1-  The source of material for instruction in radiation l                        -control and safety shall come from-the-TS, 10 CFR.19,-10 CFR 20, the Georgia Tech Radiation' Safety Manual and the written, approved Radiation Protection procedures (series 3000).
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4'.1.6.2  Th9 duration of the classroom lectures and examination-for this. subject-area will be-approximately 3 hours.-
4.~1.7    10 CFR Part 1 L
4.1~.7.1  Creation and Authority of the USNRC 4.1.7.2  The Commission -' Headquarters
              - 4.1.7.3  The Commission - Regional Offices I
 
6 5.0        ON-THE-JOB TRAINING /RRACTOR CONTROL MANIPULATIONS 5.1        Requirements for Annual Reactor Controls Manipulation 5.1.1      Each requalification candidate shall be evaluated annually on reactor control manipulation.                                                        The annual reactor control manipulations shall include .he sequence of activities listed below.
5.1.1.1    Reactor startup 5.1.1.2    Increase of reactor power to 1000 kW 5.1.1.3    Switch reactor to auto control 5.1.1.4    Allow reactor to reach temperature equilibrium 5.1.1.5    Perform power calibration 5.1.1.6    Switch reactor to manual control 5.1.1.7    Decrease reactor power to 250 kW 5.1.1.8    Switch reactor to auto control 5.1.1.9    Discussion of reactor safety systems actions between the requalification applicant and the trainer shall include:
5.1.1.9.1 Loss of Primary Coolant 5.1.1.9.2 Loss of Secondary Coolant 5.1.1.9.3 Loss of Instrument Air 5.1.1.9.4 Loss of Electrical Power 5.1.1.10  Resumption of reactor controls manipulation at this point shall include reactor shutdown.
5.1.2      The trainer for the reactor controls manipulation portion of the training shall, at a minimum, be a Senior Reactor Operator.
5.2        Requirements for Biennel Reactor Controls Manipulation 5.2.1      In  addition                        to the annual                          evaluation            of  the requalification candidates, each candidate shall be evaluated biennially (once/2 years) on other reactor controls manipulation.                      The biennial reactor control manipulations shall include the sequence of activities listed below.
 
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7 5.2.1.1  All of the activities listed above in Step 5.1.              !
5.2.1.2  'An elaboration- of Step 5.1.1. 9 _ above to include the response of the requalification candidate to- the          i activitios listed below.
5.2.1.2.1 Loss of shutdown cooling 5.2.1.2.2 Loss of a protective system channel 5.2.1.2.3 Misposition shim safety blade 5.2.1.2.4 Inability to drive a shim safety blade 5.2.1.2.5 Fuel cladding failure or radioactivity      in the reactor l                  coolant 5.2.1.2.6 Malfunction of the automatic control system 5.2.1.2.7 Malfunction of reactor coolant flow 5.2.1.2.8 Reactor trip 5.2.1.2.9 A nuclear instrument failure 6.0      DIENNIAL REQUALIFICATION EXAMINATION 6.1      Each  requalification  applicant    shall  successfully complete    a- comprehensive,  written    requalification-examination every two years.
6.2-      A passing score for-this comprehensive examination shall-be 70%.
6.3      Each requalification_ applicant shall have successfully completed the on-the-job training _as discussed in Step 5.0 during the requalification. interval.
6.4      Documentation shall be maintained showing the status of-each - requalification- candidate in the requalification program.
L l        7.0      REOUALIFICATION EVALUATION L        7.1      The Manager, Reactor Operations or his/her designee, L                  shall    perferm  the  .overall-  evaluation    off  the requalification applicant.
7.2      Records of the evaluations shall be maintained.
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7.3  A  successful    : qualification  candidate  shall  have completed the fc Lowing activities,                        j i
7.3.1 Attend (or make up) all training lectures.                ;
l 7.3.2 Receive a test score of at least 70% on each subject of the training lectures.
7.3.3 Receive a satisf actory evaluation on each annual reactor controls manipulations evaluation.
7.3.4 Receive a satisf actory evaluation on the biennial reactor controls manipulations evaluation.
7.3.5 Receive a score of at least 70% on the comprehensive, written biennial, requalification examination.
7.4  Requalification Applicant Deficiency 7.4.1 Additional training and retesting shall be given to an applicant who is found deficient in the requirements for requalification.
7.4.2 The  standard  for    successful  completion  of  the requalification program shall be the same        as  that described in Step 7.3.
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9 EVALUATION OF REACTOR CONTROL MANIPUIATION            l l
Candidate                                            Date 1
Check One:      Annual                      Biennial                I Control Manipulation or Discussion                      Sat  Unsat Reactor Startup .......................
Increase reactor power to 1000 kW .....
Switch reactor to auto control ........                _
Allow reactor to reach temp. equil.....
Perform Power Calibration .............
Switch reactor to manual control ......
Decrease reactor power to 250 kW ......
Switch reactor to auto control ........
Loss  of prLmary coolant ...............
Loss  of secondary coolant .............
Loss  of instrument air ................
Loss  of electrical power ..............
Loss of shutdown coolant ..............
Loss of a protective system channel ...
Mispositioned shim safety blade .......
Inability to drive a shim blade .......
Fuel cladding failure or Act. cool. ...
Malfunction of auto controller ........
Reactor trip ..........................
i          A nuclear instrument failure ..........
Reactor Shutdown ......................
COMMENTS:
l Candidates    (Circle One)        Pass            Fail (Evaluator's Signature)                        (Date) l l
 
                -= -.-.                  ..  ..    -    .      .
    ...o 4
10 BIENNIAL EVALUATION OF TRAINING AND TEST SCORES Candidate                                                Date Lecture
 
==Subject:==
 
1          Reactor theory and principles of operation Date(s) attended                      thru                        ,
Test score (s)
: 2.        General and specific plant operating characteristics Date(s) attended                      thru                        ;
                                                                                          ~
Test-Score (s)
L-          3.        Reactor    instrumentation  and  control    systems,  reactor  ,
l-                      protection systems and engineered safety systems.
Date(s) attended-                      thru Test Score (s)                                  __
: 4.        Normal, abnormal and emergency operating procedures l                      Date(s) attended                      thru                        :
Test Score (s)
: 5.        Technical Specifications                                          ,
Date(s) attended                      thru                        !
Test Score (s)
L            6..        Radiation Control and Safety Date(s) attended                      thru Test-Scores (s)                                                    j 7.0'      101CFR I Date Attended                          thru                      1 Test Scores                                    _
Requalification Examination (Comprehensive):
Date of Exam                  Exam Score Requalification of Candidates (Circle One)          Complete  Incomplete.
Comments:
i (Manager, Reactor Operations)              -(Date)}}

Revision as of 11:37, 30 March 2020

Requalification Program for Reactor Operators/Senior Reactor Operators,Georgia Tech Research Reactor.
ML20065S798
Person / Time
Site: Neely Research Reactor
Issue date: 01/02/1991
From:
Neely Research Reactor, ATLANTA, GA
To:
Shared Package
ML20065S796 List:
References
NUDOCS 9012260068
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