TRAINING INSTRUCTION NO. 200 ROBINSON PLANT REVISION 2

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_

PAGE TITLE REV. PROC. NO.

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


-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


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.


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.


-- OF--5 ROBTNSON PLANT OPERATOR REOUALIFTCATION PROGRAM 11 TI-200

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.


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


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

PAGE TITLE REV. PROC. NO. 9 25

- OF.- ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200

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


._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.



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:


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



(c) 3rd Quarter July .L.September

Volume 13, Emergency Plan and

Procedures

PAGE TITLE REV. PROC. NC

13 OF 25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM .11 TI-200



(d) 4th Quarter October

December

Volume 18, Fuel Follow


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


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).

10 PAGE TITLE REV. PROC. NO.


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.

PAG E TITLE .REV. PROC. NO.


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.

PAGE TITLE R EV. PROC. NO.

12 OF25 ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200

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


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


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


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

PAGE TITLE REV. PROC. NO. 22 25 ( OF ROBINSON PLANT OPERATOR REQUALIFICATION PROGRAM 11 TI-200

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:



4.2.1 The execution and overall conduct of the operator


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.


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)


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


c. Auxiliaries (Purification, Makeup, Seal H 0, Letdown, Containment, Ventilation) . .2 . W


(2) System purpose

(3) Normal operating procedures

(4) When required

(Liquid waste, solid waste, gaseous waste) A W I*


(25 System purpose (3) Normal operating procedures

(4) 10CFR20 \

(Fuel handling and storage) A

(1) Personnel requirements

(2) Monitoring requirements

(3) Hazards and precautions



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 __


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


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


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


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




(4) Analysis


(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


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




(4) Analysis


(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



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


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.


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.


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'


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


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


OF12 Robinson Plant Operator Requalification Program TT-200

Form 244


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


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

Documents

TRAINING INSTRUCTION NO. 200 ROBINSON PLANT REVISION 2