training instruction no. 200 robinson plant revision 2
TRANSCRIPT
H. B. ROBINSON
SEG PLANT
TITLE
TRAINING INSTRUCTION NO. 200
ROBINSON PLANT OPERATOR REOUALIFICATION PR(YRAM
REVISION 2
REV. APPROVED BY DATE REV. APPROVED BY DATE REV. APPROVED BY DATE
3.7 10 ig ___
77t
Recommend By: Al2 DATE
Approved By: ___
DATE
9312050472 831128 PDR ADOCK 05000261 P _PDR_
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Q 1 OF 2 5 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
1.0 PURPOSE
To establish the requirements for a requalification program for all
NRC-licensed or certified personnel at the Robinson Plant. This
program is intended to meet or exceed the requirements of 10 CFR 55,
Appendix A. It will accomplish the following:
1.1 Maintain nuclear plant operating safety and reliability
1.2 Assure that licensed and certified personnel maintain the high
-level of skill and knowledge required to accomplish routine and
emergency duties
1.3 Establish a system for evaluating aid documenting licensed and
certified personnel proficiency and competency
2.0 REFERENCES
2.1 ANSI 18.1 Paragraph 5.5.1 Retraining Program
2.2 ANSI 3.1 Paragraph 5.5.1 Retraining Program
2.3 INPO Guidelines Nuclear Power Plant Requalification Program for
Licensed Personnel (GPG-02)
2.4 FSAR Chapter 13.2
2.5 NUREG-0737
2.6 Analysis and Technology, INC Study - Section 2.5
2.7 10 CFR 55 - Appendix A, Requalification Program for Licensed
Operators
2.8 Nuclear and Fossil Training Manual
2.9 Nuclear Training Section Policy Letters
2.10 Plant Administrative Instructions
3.0 PROCEDURE
3.1 General
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-2. OF -2-5 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
3.1.1 The requalification program shall be conducted based upon
Carolina Power and Light Company requirements and the
USNRC approved requalification program.
3.1.2 All licensed and certified personnel will participate in
the retraining program. Subsequent licensees will be
integrated immediately into the on-shift training portion
and will participate in the next annual evaluation
examination. Newly licensed or certified individuals
successfully completing their NRC examination less than
six months prior to the .annual examination may be excused
from the current annual written and oral examinations at
the discretion of the Director - Training.
. 3.1.3 In accordanc, with 10 CFR 50.54. i-1, no change will be
permitted to be made to the H..B. Robinson operator
requalification program by which the scope, time allotted
for the program or frequency in conducting different
parts of the program is decreased unless specifically
authorized by the.NRC.
3.1.4 The curriculum for the requalification program will .be
based on the following:
3.1.4.1 Previous years annual written and oral
examinations
3.1.4.2 Significant plant modifications
3.1.4.3 Operating experiences at plant, other
plants, industry.
3.1.4.4 Procedure changes and issuances
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3 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
3.1.4.5 Regulations
3.1.4.6 Technical Specifications
3.1.4.7 Input from the plant shift foremen,
appropriate supervisors and managers,.
Nuclear and Simulator Training Unit and
Onsite Corporate Nuclear Safety on an
annual basis. Attachment 9 is provided for
the purpose of formally requesting this
input. A copy of Attachment 9 will also be
forwarded to N&ST Unit for their use.
3.1.4.8 Program.evaluation and performance-based
feedback from TI-904.
3.1.5 Approved lesson plans or-detailed outlines shall be
utilized on all lecture topic presentations given by the
Training Unit.
3.1.6 Instructors who teach systems, integrated responses,
transient and simulator courses are required to
demonstrate their competence to the NRC by successful
completion of a Senior Operator exam. All
licensed/certified instructors shall participate in a
requalification program.
3.1.7 If a licensed individual has not actively carried out
licensed duties for a period in excess.of four months, a
special training program and/or evaluation is required
prior to resuming licensed duties. Active status will be
maintained by participating in the annual requalification
program.
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OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
Completion of the following is required to demonstrate
that the licensee is knowledgeable of facility operation
and administration:
3.1.7.1 Review changes in operating and
administrative procedures, standing orders,
and instructions for the period of absence.
3.1.7.2 Meet with Director - Training or his
designee to discuss the material from all
requalification lectures which were missed.
3.1.7.3 Successful completion of an oral or written
examination in scope and format of the
annual requalification examination.
3.1.7.4 The facility licensee must certify to the
NRC that the operator or senior operator is
requalified. This certification shall be
initiated by plant management.
3.1.8 The annual requalification program will be approved by
the Director - Training with copies distributed to the
Manager - Nuclear Training Section and Director
Curriculum Development.
3.1.9 The training on operating experiences listed under
3.1.4.3 is presently being conducted by the Onsite
Nuclear Safety Unit. This item will be assumed at a
future date by the Training Unit.
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3.2 Operator Requalification Program
The operator requalification program consists of four (4) parts:
a. preplanned lecture series,
b. simulator retraining,
c. on-the-job training,
d. evaluation
3.2.1. Preplanned Lecture Series
The operator requalification program shall include 80
hours of preplanned training sessions conducted on a
regular and continuing basis. The scheduling shall be
such that every licensed operator will have the
opportunity to attend all lectures. Any operator who
clearly shows-he would have. passed an NRC exam on a
particular section (with an 80% or greater on that
section of the previous year'.s annual requalification
exam) will be exempt from the lecture series on that
section. If he scores less than 80% on a particular
section, he will be required to attend a lecture series
on that particular.section. Upon completion of the
classroom lectures, a topical examination on that section
will be given requiring a passing grade of greater than
or equal to 80%. The following is an outline of what
subjects may be covered, but not necessarily in the order
stated.
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6 25 OF ROBINSON PLANT OPERATOR REOUALIFICATTON PROGRAM 11 TI-200
Formal Classroom Lectures
3.2.1.1 Theory and Principles of Operations
a) Atomic and nuclear physics b) Subcritical multiplication c) Xenon and samarium effects d) Rod worth e) Boron worth f) Coefficients and defects
1) Moderator temperature 2) Fuel temperature 3) Voids 4) Pressure 5) Power
g) Shutdown margins h) Rod insertion limits
3.2.1.2 General and Specific Plant Operating Characteristics
a) Normal plant transients 1) Rod worth curves 2 Xenon transients 3 Step load changes
b) Safety Analysis 1) Review of minor accidents 2) Review of major accidents
3.2.1.3 Plant Instrumentation and Control System
a) Excore nuclear instrumentation b) Incore nuclear instrumentation c) Full length rod control d) Rod position indication e) Pressurizer pressure control f) Pressurizer level control g), Make-up water control h) Steam dump control i) Steam generator level control j) Reactor protection system k) Electrohydraulic control 1) All logics
3.2.1.4 Normal and Abnormal Procedures and Emergency Instructions
a Engineered safety systemsb Site emergency plan , c) Overall plant operating procedures
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7 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
3.2.1.5 Radiation Control and Safety
a) Nuclear radiation b) Biological effects of radiation c) 10 CFR 20 d) Radiation protection manual e) Radiation monitoring system f) Radiation procedures g) Radioactive waste disposal
3.2.1.6 Technical Specifications
a) How to use Technical Specification index, etc.
b) Safety limits, reactor core c) Heatup and cooldown limits d) Core power distribution e) Discharge limits
3.2.1.7 Chemistry
a) Chemistry control b) Radiation chemistry c) 'Specifications and criteria
3.2.1.8 Heat Transfer, Fluid Flow, and Thermodynamics
a) Basic properties of fluids and matter
b) Fluid statics c) Fluid dynamics d) Heat transfer by conduction,
convection and radiation e) Change of phase - Boiling - Hot
channel factors f) Burnout and flow instability g) Reactor heat transfer limits h) Use of steam tables
3.2.1.9 Mitigating Core Damage
a) Incore instrumentation b) Excore nuclear instrumentation c) Vital instrumentation d) Primary chemistry e) Radiation monitoring . ) Gas generation
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crew member to ensure all members complete all required
manipulations. Any licensed operator not attending a
simulator training program session will be given an oral
examination which includes a walk-through of controls,
indication, and drills. This oral examination will be
based on the simulator program session missed. The
simulator used will have a similar arrangement of
instrumentation and controls and will reproduce the
general operating characteristics of the Robinson Unit.
The simulator staff will base their programs on
recommendations and requirements forwarded to them by the
plant Director - Training andNuclear Regulatory
Commission requirements.- The program will include an
evaluation of the licensed operator's performance during
abnormal/emergency conditions. A comprehensive
evaluation of each indfvidual's performance is prepared
by the simulator staff (Attachment 12). The evaluation
is submitted to the Plant General Manager and routed to
the Director - Training for inclusion into the
individual's training records.
The following control manipulations are acceptable for
meeting the reactivity control manipulations requirements
of Appendix A, Paragraph 3.a of 10 CFR 55. The asterisk
(*) items shall be performed on an annual basis; all
other items shall be performed on a two-year cycle. Each
individual shall perform or participate in a combination
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._LO OF 2 5 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
of these control manipulations. Personnel with senior
operator licenses are credited with these manipulations
if they direct or evaluate control manipulations as they
are performed.
*3.2.2.1 Plant or reactor startups to include a
range that reactivity feedback from nuclear
heat addition is noticeable.
3.2.2.2 Plant shutdown.
*3.2.2.3 Manual control of feedwater during startup
and shutdown.
3.2.2.4 Boration or dilution during power
operation.
*3.2.2.5 .Any significant (greater than 10%) power
changes in manual rod control.
*3.2.2.6 Loss of coolant including:
a). significant steam generator leak b inside and outside containment c large and smhll, including leak-rate
determination d) saturated reactor coolant response
3.2.2.7 Loss of instrument air.
.3.2.2.8 Loss of electrical power (and/or
degraded power sources).
*3.2.2.9 Loss of core coolant flow/natural
circulation.
3.2.2.10 Loss of condenser vacuum.
3.2.2.11 - Loss of service water.
3.2.2.12 Loss of shutdown cooling.
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11 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
3.2.2.13 Loss of component cooling system or cooling
to an individual component.
3.2.2.14 Loss of normal feedwater or normal
feedwater system failure.
*3.2.2.15 Loss of all feedwater (normal and
emergency).
3.2.2.16 Loss of protective system channel.
3.2.2.17 Mispositioned or dropped control rod(s).
3.2.2.18 Inability to drive control rods.
3.2.2.19 Conditions requiring use of emergency
boration.
3.2.2.20 Fuel cladding failure or high activity in
reactor coolant or waste gas system.
3.2.2.21 Generator or turbine trip.
3.2.2.22 Malfunction of automatic control system(s)
(rod control or boron concentration
(control).
3.2.2.23 Malfunction of reactor coolant
pressure/volume control system.
3.2.2.24 Reactor trip.
3.2.2.25 Main steam line break (inside or outside
containment).
3.2.2.26 Nuclear instrumentation failure(s).
3.2.3 On-The-Job Training
On-the-job Training will be conducted in accordance with
Volume 1, Administrative Instructions, Section 4.1.6,
Shift Operations Readiness as described below:
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CLOF-21 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI 200
"It is essential to individual and crew readiness
that emphasis periodically be given to vital
information on alarm settings,.safety limits,
abnormal condition-symptoms for operation,
operating sequences, and emergency immediate
action steps."
3.2.3.1 Individual reviews, instructional sessions,
and where applicable, a walk-through of
controls and instrumentation will be
conducted so the information contained in
the volumes for that quarter are covered:
(a) 1st Quarter January - March.
Volume 1, Administrative
Instructions -Section 4
Volume 5, Abnormal Procedures
Volume 6, Emergency Instructions
(b) 2nd Quarter April - June
Volume 7, Precautions, Limitations
and Setpoints
Volume 8, Radiation Control and
Protection Manual
Volume 5, Abnormal Procedures
Volume 6, Emergency Instructions
(c) 3rd Quarter July .L.September
Volume 13, Emergency Plan and
Procedures
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13 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM .11 TI-200
Volume 5, Abnormal Procedures
Volume 6, Emergency Instructions
(d) 4th Quarter October
December
Volume 18, Fuel Follow
Volume 5, Abnormal Procedures
Volume 6, Emergency
Instructions
Conduct complete walk-through
of control room
inaccessibility (E.I.-15) and
loss of emergency
busses/station batteries
(E.I.-18)
3.2.3.2 When covering the above seven (7) volumes,
the Technical Specifications, flow
diagrams, logics and functional diagrams
will also be reviewed where applicable.
3.2.3.3 At the end of each quarter the Shift
Foreman will submit to the Director
Training the Operating Shift Quarterly
Procedure Review Record (Attachment 6).
The report will detail the information
covered for ea'ch member of the shift
operation crew, and will contain the Shift
Foreman's judgment of each operator's
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14 OF25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
familiarity with the information contained
in the volumes for that quarter, as well as
each operator's ability to take the
required action. During the 4th quarter a
complete walk-through of control room
inaccessibility (E.I.-15) and loss of
emergency busses/station batteries (E.I.
18) will be conducted individually or as a
group (this training is not available in
the Simulator Training).
3.2.3.4 Staff members holding NRC license or
certifications shall participate in the
-quarterly review of the volumes of the
plant operating manuals as detailed in
3.2.3.1 through 3.2.3.3. They will submit
the Staff Quarterly Procedure Review Record
(Attachment 7) at the end of each quarter.
This review will include a complete walk
through of control room inaccessibility
(E.I.-15) and loss of emergency
busses/station batteries (E.I.-18) which is
conducted in the 4th quarter individually
or as a group (this training is not
available in the Simulator Training).
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15 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
3.2.3.5 The Director - Training will maintain a
file of the' reports filled out by the Shift
Foremen and staff members. They will be
used in compiling qualification information
for NRC license renewal applications.
3.2.3.6 Design changes, facility license changes,
significant safety related modifications,
changes to procedures, license and
significant operating experiences, will be
screened and routed as appropriate to the
shifts and staff for review.
3.2.3.7 The staff personnel holdin an NRC operator
-license will stand an average of four (4)
hours watch in the control room per month.
If he is regularly participating in a
simulator training program, 75% of this
time can be satisfied on the simulator.
During these four (4) hours he will carry
out those duties normally conducted by
either the Shift Foreman or control room
operator. Staff-members will enter their
onshift time in the Control Room Time/PT
Record Log Book maintained in the control
room.
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3.2.3.8 During all plant operations a record will
be kept of any major reactivity changes a
licensed operator performs. The operating
shift will report these mainpulations on
the Reactor Operator Monthly Record
(Attachment 4) or SRO Non-staff Monthly
Record (Attachment 5) as appropriate.
Staff members will log their manipulations
in the Control Room Time/PT Record Log
Book.
3.2.4 Evaluation
The evaluation phase will consist of three parts:
(a) Annual written requalification examination
(b) Annual oral examination
(c) Accelerated requalification program
The annual written and oral examinations will be
conducted during scheduled training periods. Any
licensee or certified individual that fails a written or
oral exam will be removed from licensed duties and placed
in an accelerated requalification program. NRC license
pay will be governed by the respective plant procedures.
The Nuclear Regulatory Commission - Region II, (Operator
Licensing) may substitute, conduct, and regrade any or
all portions of the annual written/oral exams at their
discretion.
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3.2.4.1 Annual Written Requalification Examination
An annual written examination shall be
administered to all licensed and certified
personnel each calendar year. The purpose
of the examination is to determine each
licensed and certified individual's
knowledge and to provide a basis for
determining areas in which retraining is
required. The results will be recorded on
the requalification matrix (Attachment 13)
and be used as a reference for the next
requalification program.
The requalification examination will
utilize the basic format of that given by
the USNRC and will be operationally
oriented. The passing criteria will be 80
percent overall with no category less than
70 percent. If a licensed or certified
individual shows he is deficient in any of
the categories on the written examination,
he will be removed from licensed duties and
placed in an accelerated requalification
program using the following criteria:
3.2.4.1.1 If he scores less than 70
percent on one and not more
than two categories with an
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L 0OF25. ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
overall exam score of 80
percent, he will receive
accelerated requalification
in.those categories less than
70 percent.
3.2.4.1.2 If he scores less than 80
percent overall, he will
receive accelerated
requalification in all
categories he scored less
than 80 percent.
3.2.4.2 Annual Oral Examination
In addition to the evaluations performed
during simulator retraining (Section
3.2.2), walk-through oral examinations
shall be conducted either at the simulator
or at the operating plant on an annual
basis for selected individuals. An oral
examination form (Attachment 3, 3a, or
similar) will be used to document these
exams and the RO/SRO Oral Examination
Matrix (Attachment 14) will be completed
and be used as a reference for the next
Oral Examination.
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The selection process will be such that
each individual is examined at least once
every five years. Individuals who tend to
be weak in selected areas may be examined
more frequently. An individual who fails
to pass an oral exam will be removed from
licensed duties and placed in an
accelerated requalification program.
3.2.4.3 Accelerated Requalification Program
The licensed or certified individual with
identified deficiencies will receive a
requalification program specifically
structured to upgrade his skills and
knowledge.
3.2.4.3.1 The Director - Training shall
be responsible for
formulating and approving the
individual's accelerated
program.. The accelerated
requalification program may
involve a variety of training
exercises including:
(a) Directed self-study
(b) Oral interviews and
discussion sessions
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2 OF ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
(c) Preplanned lectures
(d) Skills training
exercise at the plant
or utilizing a
simulator
3.2.4.3.2 The program duration will be
dictated by the extent of
training required to rectify
the deficiencies and the
trainee's past performance.
3.2.4.3.3 Successful completion of the
accelerated requalification
program will be determined by
the individual successfully
completing the same type exam
(oral or written) previously
failed. This exam shall be
approved by the Director
Training.
a. The criteria for
successful completion
of a written
accelerated
requalification exam
is met by exceeding
3.2.4.1.1 or 3.2.4.1.2
as applicable.
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1. If 3.2.4.1.1
applies, the
individual
shall be re
examined on
those
categories and
must make 80
percent on each
category.
2. If 3.2.4.1.2.
applies, the
individual will
be re-examined
on an entire
exam and must
make 80 percent
overall with no
category less
than 70
percent.
b. The criteria for
successful completion
of an oral accelerated
requalification exam
is met by
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satisfactorily passing
all areas previously
graded as weak or
inadequate.
3.2.4.3.4 In the event that the
individual
does not pass the accelerated
requalification examination,
a second accelerated
requalification program shall
be structured and conducted
to correct the deficiencies
if it is thought appropriate
by the Director -Training.
In the event of a second
failure, the Director
Training shall make
appropriate recommendations
to plant management regarding
the individual's permanent
removal from licensed duties.
4.0 RESPONSIBILITY
4.1 The Operating Supervisor, Unit 2, will be responsible for the
administration and reporting of the on-shift portion of the
operator requalification program.
4.2 The Director - Training will be responsible for:
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23 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
4.2.1 The execution and overall conduct of the operator
requalification program.
4.2.2 The administration and documentation of the formal
classroom and evaluation phases.
4.2.3 Timely initiation of license renewal applications to the
NRC.
4.2.4 The proper maintenance of all records pertaining to the
.operator requalification program.
4.3 The Director of Nuclear and Simulator Training shall be
responsible for the administration, evaluation, and reporting of
the simulator training portion of the requalification program.
5.0 DOCUMENTATION
Attachments (1 through 14), listed and explained below, will constitute
the documentation for the Robinson Plant Operator Requalification
Program.
5.1 Attachment (1) Deleted
5.2 Attachment (2) RO Periodic/Comprehensive Exam Evaluation and
Grade Sheet
Attachment (2a) SRO Periodic/Comprehensive Exam Evaluation and
Grade Sheet
Attachment (3) RO Oral Examination Evaluation
Attachment (3a) SRO Oral Examination Evaluation
Attachment 2 or 2a and cover sheet of 3 or 3a will be
placed in the exam section of the individual license
personnel training folder as appropriate.
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2O2 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200
5.3 Attachment (4) RO Monthly Record
Attachment (5) SRO (non-staff) Monthly Record
Attachment (6) Operating Shift Quarterly Procedure Review
Attachment (7) Staff Quarterly Procedure Review
The Operating Supervisor, Unit 2, will forward completed
Attachments 4, 5, and 6.to the Director - Training at the
required intervals. Licensed staff personnel will
complete Attachment 7 and forward it to the Director
Training.. Attachment 6 and 7 are filedin the current.
year folders for each of these documents.
5.4 Attachment (8) Yearly Summary of Experience and Training
. C-ompleted using Attachments 4, 5, 6, and 7 and filed in
the training summary section of the individual license
personnel training-folder.
5.5 Attachment (9) Training Curriculum Development Input
Will be used by: Plant.General Manager, Corporate.
Nuclear Safety, Nuclear and Simulator Training Unit,
Managers, Supervisors and Shift Foremen to formally
provide input.to the Director - Training for
consideration in the development of the training
curriculum for the licensed requalification program.
This attachment should be completed-and forwarded by
November 1 of each year for inclusion in the following
year's program and filed under NTS number 4208(D) for use
by the instructors in the development of the following
year's requalification program.
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5.6 Attachment (10) Results of Annual Licensed Operator Exam
.(Example)
Attachment (11) Accelerated Requalification Program (Example)
These documents are placed in NTS file number 4208(F) and
also in the examination record section of the
individual's .file of personnel named in these
attachments.
5.7 Attachment (12) Simulator Evaluation. (Example)
Will be placed in NTS file number 4210(J) and in the exam
section of the individual license personnel training
folder.
5.8 Attachment (13) Requalification' Matrix
Attachment (14) RO/5RO Oral Examination Matrix
Will be placed in NTS file number 4208(F).
5.9 Classroom records will be completed and filed in accordance with
TI-906.
PAGE TITLE REV. PROC. NO. Attachment 1
OF 1 FOBTINNI ETOR FTATPTCATTON PROGRAM 11 TI-200
DELETE
PAGE TITLE . REV. PROC. NO. Attachment 2
OF Robinson Plant Operator Requalification Program 11 TI-200
CAROLINA POWER & LIGHT COMPANY REACTOR OPERATOR H. B. ROBINSON STEAM ELECTRIC PLANT EVALUATION/GRADE SHEET
Taken By (PERIODIC)(COMPREHENSIVE).EXAM
Exam No. DATE
Total Section Points/Points Grade
1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer, and Fluid Flow /
2. Plant Design Including Safety and Emergency Systems
3. Instruments and Controls
4. Procedures - Normal, Abnormal, Emergency, and R adiological Control .
Average.
INSTR UCTIO NS
1. Staple question sheets on top of answer sheet.
2. The point value for each question -is indicated.
3. Only one person allowed out of a room at a time.
4. To pass a comprehensive exam you must receive greater than or equal to 70% on each category and greater than or equal to 80% overall. To pass a periodic exam you must receive greater than or equal to 80% on each category.
5. Time limitation - 6 hours on a comprehensive exam.
6. Show category and question number with answer (i.e., 2-1).
All work done on this exam is my own, I have neither given nor received aid.
Applicant Signature
Provide written evaluation of all sections for which a score of less than 70% is achieved:
(Continue on separate sheet if necessary)
-1rector - Iraining.
PAGE TITLE REV. PROC. NO. 1 1 - Attachment 2(a)
OF Robinson Plant Operator Requalification Program 11 TI-200
CAROLINA POWER & LIGHT COMPANY SENIOR REACTOR OPERATOR H. B. ROBINSON STEAM ELECTRIC PLANT EVALUATION/GRADE SHEET
Taken By (PERIODIC)(COMPREHENSIVE) EXAM
Exam No. DATE
Total SECTIO N Points/Points Grade
5. Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics /
6. Plant Systems: Design, Control and Instru mentation /
7. Procedures- Normal, Abnormal, Emergency, / and Radiological Control
8. Administrative Procedures, Conditions, and Limitations
Average
INSTR U CTIO NS::
1. Staple question sheets on top of answer sheet.,
2. The point value for each question is indicated.
3. Only one person allowed out of a room at a time.
4. To pass a comprehensive exam you must receive greater than or equal to 70% on e-ach category and greater than or equal to 80% overall. To pass a periodic exam you must receive greater than or equal to 80% on each category.
5. Time limitation - 6 hours on a comprehensive exam.
6. Show category and question number with answer (i.e., 3-1).
All work done on this exam is my own, I have neither given nor received aid.
Applicant Signature
Provide written evaluation of all sections for which a score of less than 70% is achieved:
(Continue on separate sheet if necessary)
Director - Training
-PAGE TITLE REV. PROC. NO. ATTACHMENT (3),1T20
OF 6 RBINSON PLNT OPERATOR RMUALIFICATION PROGRNA 11 TI-200
CAROLINA POWER & LIGHT COMPANY REACTOR OPERATOR ORAL EXAMINATION CHECK SHEET H. B. ROBINSON STEAM ELECTRIC PLANT
CANDIDATE EXAMINER
DATE PASS/FAIL
1. Understanding of Reactivity Effects A I*
a. Subcritical multiplication & prediction of critical
b. Knowledge of when critical
c. Instrument behavior and response
d. Heating effects, reactivity coefficients e. Xe, Sm, burnup, Pu
f. Delayed neutrons g. Use of facility curves, tables & charts'
2. Instrumentation Characteristics and Design
a. Nuclear Instrumentation (Excore) . A It
(1) Detector characteristics (source, inter., power)
(2) Over & under compensation effects, discriminator
(3) Channel components and/or hardware
(4) Requirements: startup, power,bypass (5) Connections to safety systems
* (6) Response to malfunctions .
b. Nuclear Instrumentation (Incore) A
(1) Detector characteristics
(2) Channel components and/or hardware
(3) Requirements
(4) Operating procedures
c. Process Instrumentation (Incore)A A
(1) Detector location and function (2) Recorder or indicator location
REMARKS: (Mandatory if W is checked)
* A, Adeuate; W, Weak; I, Inadequate
PAGE TITLE REV. PROC. NO. .Attachment (3)
T-0 '2OF ROBINSON PLANT OPERATOR REDUALIFICATION PROPAM 11 TI200
3. Operating Characteristics
a. Reactor and Plant Control-System
(1) Manual operation A W
a. Rod speed and programming
b. Chemical shim requirements
c. System capabilities
d. Mechanical operation of .rod drive
(2) Automatic operations A W
a. Conditions that must be satisfied
b. Input signals and deadband
c. Rod blocks and runbacks
b. Reactor and Plant Response (if necessary have the applicant trace transients of pressure, temps.., reactivity, levels, etc., for a change in a given parameter. Use reverse side).
A I
(1) Load increade (2) Load decrease (3) Other (Specify) (4) Other (Specify)_ _
4. Facility Equipment Design and Characteristics
a. Heat Removal Normal and Decay (Primary . Coolant & Pressurizer, Residual Heat Removal, Steam Dump)
A
(1) Equipment location
(2) Flows, temps., pressures
(3) Requirements _
(4) Chemistry
(5) Normal operating procedures .
(suggested procedures)
REMARKS: (Mandatory if W is checked).
PAGE A TITLE REV. PROC.NO. .. Attachment (3) T-0 OF ± RMSTRMf79 DTANT ODrTOR PFnTnnTTPTGr(1rT1NT TI-20 0
4. Facility Equipment Design and Characteristics (Continued)
A WI
a. Cold shutdown to or from hot shutdown
b. Hot shutdown to full power,
c. Boration, deboration
d.. Pressure and level control
e. Chemical addition
f. Other (specify)
g. Familiar with proper checklist
h. Understands what he is checking
i. Understands why he is checking it
b. Safety and-Emergency (Safety Injection, Containment Spray, Component Cooling, Emergency Boration, Pressure Relief)
A W 1 (1) Equipment location
(2) Flow .paths .
(3) When required
(4) Why required
(5) Initiating signals
(6) Operating procedures
c. Auxiliaries (Purification, Makeup, Seal H 0, Letdown, Containment, Ventilation) . .2 . W
(1) Equipment location
(2) System purpose
(3) Normal operating procedures
(4) When required
(Liquid waste, solid waste, gaseous waste) A W I*
(1) Equipment location
(25 System purpose (3) Normal operating procedures
(4) 10CFR20 \
(Fuel handling and storage) A
(1) Personnel requirements
(2) Monitoring requirements
(3) Hazards and precautions
(4) Operating procedures
REMARKS: (Mandatory if W is checked)
PAGE T ITLE REV. PROC. NO. Attachment (3)
4 OF ROBINSON PLANT OPERATOR REUALIFICATION PROGPAM 11 TI-200
4. Facility Equipment Design and Characteristics (Continued)
d. Electrical
(1) Normal A
a. Sources .
b. Major equipment supplied
c. Operating procedures
d. Requirements
(2) Emergency. A I*
a. Sources
b. Automatic transfer features c. Equipment supplied
d. Requirements
e. Operating procedures
e. Secondary A W*
(1) Flows, temps., pressures
(2) Primary to secondary leak detection
(3) Equipment -function __
(4) Operating procedures
5. Periodic Tests (select at. least one) A I*
a. Familiar with the procedure
b. Understands what he is checking
c. Understands why he is checking it
6. Abnormal operations (suggested incidents) turbine trip, reactor trip, dropped rod, pipe break, uncontrolled steam extraction, other (specify).
a. Alarms and responses A IA
(1) Control room identification (2) . Automatic action
b. Emergency and abnormal procedures A IA
(1) Immediate operator action _
(2) Follow-up action (3) Notification (Plant Manager, NRC)
REMARKS: (Mandatory .if W is checked)
PAGE TITLE REV. PROC. NO. Attachment (3) 5 OF 6±j RBINSON PLANT OPERATOR REQUALIFICATION PROGRW 11 TI-200
6. Abnormal operations (suggested incidents) turbine trip, reactor trip, dropped rod, pipe break, uncontrolled steam extraction, other (specify). (Continued)
(In addition to the above, select at random at least three annunciator plates. Ask for setpoint, probable cause, operator action.)
(1) (Specify) (2) (Specify)
(3) (Specify) (4) (Specify)
c. Facility Emergency Plan
(1) Control operator's duties (2) Evacuation routes and points
7. Radiological Safety
a. Equipment.
(1) Installed (area, process) A I
a. Type of detector b. Purpose
c. Setpoint
(2) Portable A 'W
a. Radiation detected b. Range
_
c. Can use the instrument
b. Characteristics AW 1
(1) Ion chamber (2) G.M. Tube
(3) Neutron monitor_ _
(4) Scintillation__
REMARKS: (Mandatory if W is.checked)
GEA t ta c ment (3) REV. PROC. NO.
P OF TNSON PLANT OPERATOR REUALIFICATTON PRTI-200
7. Radiological Safety (Continued)
c. Procedures and practices A W I*
(1) 10CFR20 (2) Facility limits.
(3) Facility procedures (4) Personal practices
REMARKS: (Mandatory if W is checked)
8. Knowledge of authorities, responsibilities and general comments based on your observation of applicant during the oral exam.
PAGE ATTACINH (3a) REV. PROC. NO.
1 OF ROBINSON PLANT OPERATOR REQUALIFICATION PROGRA 11 TI-200
CAROLINA POWER & LIGHT COMPANY SENIOR REACTOR OPERATOR ORAL H. B. ROBINSON STEAM ELECTRIC PLANT EXAMINATION CHECK SHEET
CANDIDATE EXAMINER
DATE PASS/FAIL
1. Control Room
a. Shift turnover A A . I
(1) Logs and records
a. Shift Foreman
b. Operating
c. Jumper and lifted leads
d. Surveillance e. Tagging
f. Key control
g. Maintenance
b. Control Room Reference Data A W
(1) Technical specification
a. Changes
b. Reporting requirements c. d.
.(2) Procedures
(3) Radiation protection
a. Release rates b. Exposure limits c. Radiation work permits
(4) Piping and instrumentation drawings (5) Computer
(6) Estimated critical position determination
REMARKS: (Mandatory if W is checked)
PAGE Attac eh (3a) REV. PROC. NO. OF 5 ROBINSON PLANT OPERATOR REOUA ICATION POGRAM 11 TI-200
2. Responsibility and Authority A W
a. Emergency Plans
(1) Duties
(2) Types of emergencies
(3) Evaluation criteria
(4) Personnel assignments
b. Plant Operations A W
(1) Startup
(2) Shutdown
a. Normal b. Automatic c. Outside control room d. Hot standby; cold shutdown
c. Fuel Handling. A W
(1) Storage;
(2) Refueling
d. Surveillance Testing
(1) Instrumentation and Control (2) Other (Specify)
REMARKS: .(Mandatory if W is checked)
PAGE TITLE REV. PROC. NO Attachment (3a) 3 OF 5 ROBINSON PLANT OPRATOR REQUALIFICATION PROGRAM 11 TI-200
3. Discussion
a. Transients .(Specify) A
(1) Components (2) Instruments
a. Control room indications b. Automatic control
(3) Reactor Protection
a. Automatic actions b. Alarm setpoints
(4) Analysis
a. Coefficient effects b. Safety system interactions
(5) Procedures
a.
b.
b. Reactivity Effects A W 1
(1) Power increases.and.decreases (2) Axial and radial limits, bases (3) Long term exposure effects (4) Xenon oscillations
(5) Shutdown margin
(6) Dropped rod
(7). Subcritical multiplication
(8) Stuck rod
c. Thermodynamics and Hydraulics A W
(1) Steam tables
(2) Pressure-Temperature curves (3) Instrumentation (4) Pump characteristics (5) Saturation conditions (6) Natural circulation
(7) Water hammer (8) Heat balance
REMARKS: (Mandatory if W is checked)
PAGE TITI F REV. PROC. NO. Attachment 3(a) Q OF 5 RBINSON PLANT OPERATOR REQUALIFICATION PROGRAM TI-200
3. Discussion
a. Transients (Specify) A W I*
(1) Components
(2) Instruments
a. Control room indications b. Automatic control
(3) Reactor Protection
a. Automatic actions b. Alarm setpoints
(4) Analysis
a. Coefficient effects b. Safety system interactions
(5) Procedures
a. b.
b. Reactivity Effects A W1
(1) Power increases and decreases (2) Axial and radial limits, bases (3) Long term exposure effects (4) Xenon oscillations (5) Shutdown margin (6) Dropped rod
(7) Subcritical multiplication
(8) Stuck rod
c. Thermodynamics and Hydraulics A W
(1) Steam tables (2) Pressure-Temperature curves (3) ..Instrumentation (4) Pump characteristics
(5) Saturation conditions (6) Natural circulation (7) Water hammer (8) Heat balance
REMARKS: (Mandatory if W is checked)
PAGE TITLE REV. PROC. NO. - - Attachment (3a) T
OF 5 ROBINSON PTANT OPERA'TR 'rnJALIFICATInN PP YAM TI-200
3. Discussion
a. Transients (Specify) A W I*
(1). Components
(2) Instruments
a. Control room indications b. Automatic control
(3) Reactor Protection
a. Automatic actions b. Alarm setpoints
(4) Analysis
a. Coefficient effects b. Safety system interactions
(5) Procedures
a. b.
b. Reactivity Effects
(1) Power increases and decreases. (2) Axial and radial limits, bases (3) Long term exposure effects
(4) Xenon oscillations (5) Shutdown margin (6) Dropped rod _
(7) Subcritical multiplication
(8) Stuck rod
c. Thermodynamics and Hydraulics A W 1*
(1) Steam tables _ _
(2) Pressure-Temperature curves (3) Instrumentation (4) Pump characteristics (5) Saturation conditions (6) Natural circulation. (7) Water hammer (8) Heat balance
REMARKS: (Mandatory if W is checked)
PAGE TITLE REV. PROC. NO. Attachment 4
1 OF 1 Robinson Plant Operator Requalification Program 11 TI-200
REACTOR OPERATOR MONTHLY RECORD
Month-. . Na me:
2. Time spent on RTGB hours
3. Evolutions performed (PT's, casualties, include brief description)
A.
B.
C.
D.
4. Number of power level changes greater than 10% with rods in manual
5. Number of startups to point of adding heat.
6. Number of orderly shutdowns (nottrips).
7. Manual control of S/G's on plant loading.
8. M anual control of EH system during plant loading. _
9. Operation of manipulator during refueling. hrs.
10. Boration during power operation
11. Dilution during power operation
12. List any additional training received (courses, lectures, etc.):
B.
D..
E.
PAGE TITLE REV. PROC. NO. 1 2 Attachinent 5
OF - ROBTNcoN PTANT OPpuAnnP PUALTFTCATTlN PrmAM 11 TI-200 SRO NON STAFF MONTHLY RECORD
Month
1. . Name:
2. Time spent in direct supervision of RTGB. hrs.
3. Time spent on RTGB. _hrs.
4. Evolutions supervised (PT's casualties, etc., - include brief description
if.needed)
A.
B.
C.
D.
Use a separate sheet for any additional.
5. Evolutions performed on R GB (PT's, casualties, etc. include brief
description if needed)
A.
B.
C.
Use a separate sheet for any additional.
6. Number of power level changes '>10% with rods in manual.
A. Supervised
B. Performed
7. Number of startups to point of adding heat
A. Supervised
B. Performed
8. Number of orderly shutdowns
A. Supervised
B. Performed
9. Supervised refueling operations in : C.V. hrs.
PAGE TITLE REV. PROC. NO. 2 2Attachment 5
- OFI. Robinson Plant Operator Requalification Program 11 TI-200
SRO NON-STAFF MONTHLY RECORD
10. Supervisd/Operated S/G's in manual during plant startup/shutdown
11. Supervised/Operated-EH in manual during plant startup/shutdown
12. Supervised/Operated boration during power operation
Supervised/Operated dilution during power operation
13. List any additional training received (courses, lectures, etc.):
A.
B.
C.
't'
PAGE TITLE REV. PROC. NO. 1 1 Attachment 6
OF Robinson Plant Operator Requalification Program 11 TI-200
OPERATING SHIFT QUARTERLY PROCEDURE REVIEW RECORD
Quarter# Date:
A. Shift No., consisting of the following personnel, has reviewed the Plant Operating Manuals for this Quarter (listed below) and Technical Specifications, flow, logic, and functional diagrams where applicable.
Quarter #1 (Jan. - March) Quarter #3 (July - Sept.) Vol. #1 - A.I. Vol. #13 - E..Plan Vol. #5 - A.P. Vol. #5 - A.P. Vol. #6- E.I. Vol. #6 - E1.
Quarter #2 (April - June) Quarter #4 (Oct. - Dec.) Vol. #7 - P.L.S. Vol. #18 - Fuel Follow V ol. #8'- Radiation Control Vol. #5 - A.P. Vol. #5 - A.P. Vol. #6 - E.I. Vol. #6 - E.I. Conduct complete walk-through of
control room inaccessibility (E.I.-15) and Loss of Emergency Bussess and/or Section D C Batteries (E.I.-18)
1. 5.
2. 6.
3. 7.
4. 8.
B. With the exception of the personnel listed below, all members of this shift are familiar with these procedures and possess the ability to take required actions as covered therein.
1. _3.
2. 4.
*Additional Remarks:
*Remarks are required for any person listed in Section B.
Shift Foreman Operaing Supervisor
ROUTE TO DIRECTOR -TRAINING WHEN COMPLETED.
PAGE TITLE REV. PROC. NO.
1LOFI1 Robinson Plant Operator Requalification Program 11 TI-200
STAFF QUARTERLY PROCEDURE REVIEW RECORD
Period From: To:
Quarter #
In accordance with the Plant 0 perating M anual, V olu me 1, section 4.1.6, I have reviewed the Plant Operating Manuals for this Quarter (listed below) and Technical Specifications, flow, logic, and functional diagrams where applicable.
Quarter #1 (Jan. - M arch) Quarter #3 (July - Sept.) Vol. #1- Al. Vol. #13 - E. Plan Vol. # 5 - A.P. Vol. #5 - A.P. Vol. #6 - El. Vol. #6 - E.I.
Quarter #2 (April - June) Quarter #4 (Oct.- Dec.) Vol. #7 - P.L.S. Vol. #18 - Fuel Follow Vol. #8- Radiation Control Vol. #5- A.P. Vol."#5A.P. Vol. #6 - E.I. V ol. #6 - El. Conduct'complete walk-through of
control room inaccessibility (E.I.-15) and Loss of Em erg. B usses and/or Station DC Batteries (E.I.-18)
Name Title
D ate
ROUTE TO DIRECTOR -TRAINING WHEN COMPLETED.
PAGE TITLE REV. PROC. NO. Attachment 8
CK WOF . nRTM'rnN PTANT OPERATR RMTUAT.TFTCATTnN PwrrtM 11 TI-200
YEARLY SUMIARY OF. EXPERIENCE AND TRAINING
SRO, RO, and REPLACEMENT CANDIDATES NAME
YEAR
Licensed RX MANUAL Manip. PT. Quarter Month Duty Hrs. SU ISD 10% P.C., SG's EHC Bor. Dil. Crane Check-Off .R I
JAN
.EBI .1. MAR
APR MAY
JUNE
JULY
AUG
SEPT
OCT. .! I_____ _ _ __
DEC _
ADDITIONAL TRATNING
1. hours
2. hours
hours
5. hours
hours
7. _ hours
8. hours
9. hours
.10 .hours
11. hours
hours
13. hours
14. hours
PAGE TITLE REV. PROC..NO. Attachment 9
1 OF 1 ROBI'SON PLANT OPERATOR PB ALIFICATION PROGRAM 1 TI-200
TRAINING CURRICULUM DEVELOPMENT INPUT
FILE: 4208 (D)
TO:_ Director-Training
FROM:
. (Plant General Manager, Corporate Nuclear Safety, Nuclear Simulator Training Unit, Managers, Supervisors, and Shift Foreman)
SUBJECT: Input for the Development of the Training Curriculum for the 19 Licensed Requalification Program
Please list belcw the items you would like considered for inclusion in the listed areas:
1. Classroom lectures desired based on observed weaknesses or other appropriate reasons. (In addition to routine requalification requirements).
a.
b.
2. Transients or evolutions desired on simulator (In addition to routine requalification requirements).
a.
.b.
3. Recommendations on items not covered under 1. or 2.
a.
b.
C.
Signed
RESU OF ANNUAL LICENSED OPERATINCAM
PAGE TITLE REV. PROC. NO. 1 1 Attachment 10'
OF Robinson Plant Operator Requalification Program 11 TI-200
Form 244
Carolina Power & Light Company
H. B. ROBINSON SEG PLANT Company Correspondence P. O. BOX 790
HARTSVILLE, SOUTH CAROLINA 29550
DATE
File: N TS-4208(F) Serial:
MEMORANDUM TO: Operating Supervisor, Unit.No.2
FR 0 M: Director -Training
(SUBJECT: Results of 1983 Annual Exam No. 2
The 1983 Annual R 0/SR 0 No. 2 exams have been graded and reviewed. In accordance with Section 3.2.4 of TI-200, the below listed personnel should be removed from licensed duties and placed in an accelerated requalification program. The accelerated requalification program will begin on (date to be provided).
Persons needing accelerated requalification:
Reactor Operators Senior Reactor 0 perators
WMB/gbm
ACCELERATED REQUALIFICATION PROGRAM
* PAGE TITLE REV. PROC. NO.
1 1 Attac ent 1 OF Robinson PlantOieratorReaualification Proram 11 TT-200
Form 244
Carolina Power & Light Company
H. B. ROBINSON SEG PLANT Company Correspondence .. P. 0. BOX 790
HARTSVILLE, SOUTH CAROLINA 29550
DATE
File: NTS-4208(F) Serial:
MEMORA NDU M TO: Operating Supervisor, Unit No. 2
FROM: Director- Training
SUBIJE CT: Accelerated Requalification Program
As a result of their performance on the 1983 Annual Requalification Examination, certain individuals were required to be removed from licensed duties and placed in an Accelerated Requalification Program.
The purpose of this memorandum is to inform you that the following individual(s) have successfully completed the prescribed Accelerated Requalification Program (Section 3.2.4 of TI-200) on (date) and are again eligible to perform licensed duties.
Grade sheet(s) are attached.
Please let me know if you need further information.
CAB/gbm
Attachment .
cc: Manager, NTS
PAGE TITLE REV. PROC. NO. Attachment 12
OF12 Robinson Plant Operator Requalification Program TT-200
Form 244
Carolina Power & Light Company
Barris Energy & Environmental Center Company Correspondence Route 1, Box 327
New Hill, North Carolina 27562
Confidential
File: NTS-4210(J) Serial:
MEMORANDUM TO: Plant General Manager
FROM: Director- Nuclear and Simulator Training,
SUBJECT:. H. B. Robinson Licensed Operator Retraining (Simulator)
A one-week simulator retraining course was conducted at the Harris E&E Center on the Shearon Harris si m ulator from August 30, 1982, to Septe m ber 3, 1982. Participating members were Mr. and Mr.
The course emphasized the following:
1. ECPs and reactor start-ups.
2. Normal and infrequent evolutions with main steam, condensate, feed water, CV CS, and electrical systems.
3. Em ergency Instructions E-I-1, 2, and 3.
4. Abnormal procedures.
5. Multiple casualties.
6. Natural circulation.
The following is a list of the reactivity manipulations with rod control in manual and reactor S/Us conducted by each individual.
M anipulations Start-ups Supervised Performed Supervised Performed
6 4 2 1 4 6 12
PAGE TITLE REV. PROC. NO.
2 2 Attachment 12 Robinson Plant Onerator ReqnnlificAtion Progrrn 11 TI-200
Plant General Manager - 2 Date
An operating examination was administered Thursday morning. The exam was approximately four hours in duration and consisted of several casualties. The casualties were:
1. Inadvertent dilution.
2. P Z R safety failure (4 percent open).
3. Safety injection train failure with an AT WS event.
(Name) - Assignment- Reactor Operator
(Name) has satisfactorily completed the simulator exam. He is an exceptionally sharp operator with the ability to analyze transients and malfunctions accurately and consistently. Even though he was at a disadvantage by being the only operator, he performed all evolutions well.
(Name) - Assignment - Shift Foreman
(Name) is an excellent supervisor. His knowledge of procedures and technical specifications is very good. When coupled with his plant experience, even with a handicap of only one other operator for the week, his analysis and control of plant evolutions were excellent. (Name) performance on the exam was satisfactory.
B R/jsg
! PAGE TITLE REV. PROC. NO.
ROBINSON PIANT OPERATOR REQALIFICATEON PRCGRAM C OFZ Attachment 13 11 TI-200
REQUALIFICATION MAT (Operator Performance) RO
Year SRO Section- 1i9
Operator Nam - r I
0RO SRO Z (D Year/Exam Type 2 23 4 5 6 7 18
w F-1
CN
H
------
#ooo
40O
Example: # Passe II--- - Average for that section
R. 0. ORAL EXAMINATION MATRIX
o c'1. Reactivity Effects---------- ----- - - - - -- -
zo
H. 2. Instrumentation
a) N.t Remval
b) N.I. (Incore)
c) Proc. Tnstru. (Inmre--
3. Op. Characteristics
6 .ARx. &Pl f- Oper . b) Rx. & Pl.Res.
P4. Ecruip. Design & Char.------------- - - -
C a) Heat Removal-------------- --- - - - -------------
7.
b) Safety & E1Ter.- - - - - - - - - - - - - - - - - - - - - - - - -
c) Auxiliaries'----------------------------- ~ - - - -
d) Electrical
e) Secondary - - - -- - - - - - - - - - - - - - - - -
5. Periodic Tests --- ---- ---
6. Abnormal Oper.
OJ
a) larms..& Res-
b) E.T. &A. Ps - - - -- -l
c) R-aerafengy Plan
~7.RADCON Safety
a) Bquirrnent.- -- - - - - - - - -- - - -
b) Characteristics - --- - -- - - - - - - - -
c) Proce. & Practices _ - - - - - - - - - - - - - - - - - - - - - - - -
Q9 LL < 0 CL I L
6,
S. R. 0. ORAL EXJAMINATION MATRIX'
zo~ Ci 1 Control RO
0
CC
Cr E- a) Logs& Records'
b) C. R. Ref. Data
*J j 2. Respons. &Athority
*a) Elner. Plans'
*b) Plant Oper.
> c) Fuel Handling
*d) Surveillance Test
3.Discussion
a) Transients------------------------------------------
(Specifyh------------------------------------------
b) Reactivity Effects
c) Thermo& Hvd. a)3. Discussion 4Re-- -------
a) Transients-------aj) Transi ents --
(Speify):
b) Reactivity Effects .- --- - - -
c) Thermo & Hydr. a) Tra~nsintsc
S(Specify) : -*
b) Reactivity Effcts -- -
c) Themo & Hvdr. .Z. .------------- - - - - ~- - - - - - - -
.11
,' ... ...0