ML18018B666

Rev 0,Vol I to TI-200, Licensed Operator Requalification Program

ML18018B666
Person / Time
Site:	Harris
Issue date:	05/18/1984
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18018B665	List: ML18018B664 ML18018B666
References
TI-200, NUDOCS 8406120233
Download: ML18018B666 (51)

Text

CPS,L.

HARRIS TRAINING UNIT TRAINING INSTRUCTIONS MANUAL VOLUME:

Tl NUMBER:

TI-200 REVISION:

0

~ TITLE:

Licensed Operator Requalific'ation Program REV.

APPROVED BY

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HARRIS TRAIN 8 INSTRUCTIONS MANU I

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'0 TITLE Licensed Operator Requalification Program PAGE of 1

15 1.0 PURPOSE To establish the requirements for a requalification program for all NRC licensed or certified personnel at the SHNPP.

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 o'f skill and. knowledge required to accomplish routine and emergency duties 1.3 Establish a system for evaluating and 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'lant 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 10CRF55 Appendix A, Requalification Program for Licensed Operators 3.0 PROCEDURE 3.1 General 3.1.1 The requalification program shall be conducted based upon Carolina Power

& Light Company requirements and the USHRC approved requalification program.

3.1.2 All licensed and NRC 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 or oral examinations.

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15 of

3. 1.3 In accordance with 10CFR50,54.i-l, no change will be permitted to be made to the SHNPP 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 vill be based on the folloving:

I 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 3.1.4.5 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.

3.1.4.8'rogram evaluation and feedback from TI-904'.

3. 1.5 Lesson plans or detailed outlines shall be utilized on all lecture topic presentations in the classroom.

3.1.6 Instructors who teach

systems, integrated responses, transient and simulator courses are required to have held or hold a valid SRO license or have been certified by the NRC.

All licensed/certified instructors shall participate in a requalification program.

3.1. 7 The following requirements demonstrate that the licensee is knovledgeable 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.

,HARRIS TRAINles INSTRUCTIONS MANU+

TITLE L-200 V 'icensed Operator Kequalification Program VOL PAGE15 of 3.1.7.3 Successful completion of an oral or written examination in scope and format of the 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."

C ~

d.

3.2 Operator requalific'ation program The operator requalification program consists of four (4) parts:

a.,

Preplanned lecture series, b.,

Simulator retraining, On-the-job training Evaluation 3.2.1 Preplanned Lecture Series The operator requalification program will include 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of preplanned training sessions conducted on a regular and continuing basis.

The scheduling will be such that every licensed operator will have the opportunity to attend all lectures.

Any operator who scores an 80% or greater. on a requal exam or an NRC exam on a particular section, can be exempted 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.

I Formal Classroom Lectures

'.2.1.1 Theory and Principles of Operations a)

.b) c)

d) e)

Atomic and nuclear physics Subcritical multiplication Xenon and samarium effects Rod worth Boron worth

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Coefficients and defects 1)

Moderator temperature 2)

Fuel temperature 3)

Voids 4)

Pressure 5)

Power g)'hutdown margins h)

Rod insertion limits

.3.2.1.2 Geneial and Specific Plant Operating Characteristics a) b)

Normal plant transients 1)

Rod worth curves 2)

Xenon transients 3)

Step load changes Safety'Analysis 1)

Review of minor accidents 2)

Review of major accidents 3.2.1.3 Plant Instrumentation and Control System a) b)

c) d)

e)f) g)

h)i) 3)

k) 1)

Excore nuclear instrumentation Incore nuclear instrumentation Full length rod control Rod position indication Pressurizer Pressure control Pressurizer level control Make-up ~ater control Steam dump control Steam generator level control Reactor protection system Zlectrohydraulic control All logics

3. 2..1.4 Normal and Abnormal "Procedures and Emergency Instructions a)

Engineered safety systems b)

Site emergency plan c)

Overall plant operating procedures 3.2.1.5 Radiation Control and Safety a)

Nuclear radiation b)

, Biological effects of radiation c) 10CFR20 d)

Radiation protection manual e)

Radiation monitoring system f)

Radiation procedures

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15 of 3.2.1.6 Technical Specifications a) b)

c) d)

Safety limits, reactor core Heatup and cooldown limits Core power distribution Discharge limits 3.2.1.7 Chemistry a)

Chemistry control b)

Radiation chemistry c)

Specifications and criteria 3.2.1.8 Quality Assurance Responsibilities 3.2.1..9 Heat Transfer, Fluid Flow, and Thermodynamics a) b)

c)

(j) e)f) g)

Basic properties of fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase Boiling Burnout and flow instability Reactor heat transfer limits 3.2.1.10 Mitigating Core Damage a) b)

c)

(j) e)f)

Incore instrumentation Excore nuclear instrumentation Vital, instrumentation Primary chemistry Radiation monitoring Gas generation 3.2.1.11 Pressurized Thermal Shock a) b)

c) d)

e)

Brittle fracture and the reactor vessel Heatup and cooldown curves Transients and accidents with PTS concerns Case histories with PTS concerns PTS concerns in various operating procedures 3.2.1.12.Significant modifications to existing systems or installation of new systems

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VOI PAQE 6

15 of 3.2.1.13 Significant plant operating experiences (e.g.,

LERs) other plant's operating experiences and industry operating events.

3.2.1.14 Significant revisions to existing plant

~

procedures and issuance of new procedures.

3.2.1.15 Plant Systems 3.2.2 Simulator Retraining Carolina Pover 6 Light Company requires that each licensed and NRC certified individual receive approximately 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> of training on a simulator each year.

This training is usually divided into two 32 hour3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> sessions.

Simulator training encompasses training on control, auxiliary emergency

systems, procedures, technical specifications, transient conditions, reactivity manipulations, and operator skills.

During the simulator training, the shift team concept's utilized.

Past-experience critiques are conducted at the control panel following the training exercises.

The simulator staff maintains a record of all manipulations performed by each crev member to ensure all members complete all required manipulations.

Any" licensed operator not attending a simu'lator 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 similar arrangement. of instrumentation and controls and vill reproduce the general operating characteristics of the SHNPP Unit.

The simulator. staff vill base their programs on recommendations and requirements forwarded to them by the plant Director-Training. and Nuclear Regulatory Commission requirements.

This program will be concluded with evaluation of the licensed operator's performance during abnormal/emergency conditions.

A comprehensive evaluation of each individual's performance is prepared by the simulator staff.

The evaluation is submitted to the Plant General Manager and routed to the Director-Training for inclusion into the individual's training records.

The folloving control manipulations are acceptable for meeting the reactivity control manipulations requirements of Appendix A, Paragraph 3.a of 10CFR55.

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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15 of 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) c)

significant st/am generator leak inside and oudh'kde containment large and small, including leak-rate determination saturated reactor coolant response 3.2.2..7 Loss of instrument air 3.2.2.8 3.2.2.9 Loss of electrical power (and/or degraded power sources)

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

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• 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 3.2.2.19 Inability.to drive control rods 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 or 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 3.2.2.25 Reactor trip Main steam line break (inside or outside containmenL) 3.2.2.26 Nuclear instrumentation failure(s) 3.2.3 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 with the exception of the 1-3 months during each operating cycle when the unit is being refueled:

On-The-Job Training 0

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

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Licensed 0 erator Re ualification Pro ram PAQK 9

15 of (a) 1st Quarter January March (1)

Administrative Instructions Conduct of Plant Operations (2)

Abnormal Procedures (3)

Emergency Instructions, flow charts, EPP's and FRP (b) 2nd Quarter April June (1)

Precautions, Limitations and Setpoints (2)

'Radiation Control and Protection Manual (3)

Abnormal Procedures (4)

Emergency Instructions, flow charts, EPP's and FRP (c) 3rd Quarter July September (1)

Emergency Plan and Procedures (2)

Abnormal Procedures (3)

Emergency Instructions, flow charts, EPP's and FRP (d) 4th Quarter.,

October December (1)

Fuel Follow (2)

Abnormal Procedures (3)

Emergency Instructions, flow charts, EPP's and FRP-(4)

Conduct complete walk-through of Control Room Inaccessibility Procedure

3. 2. 3'2 During the 1-3 months that the unit is being

refueled, the quarterly revie~ is not required,,

but the volumes for that quarter will be required to be reviewed during the next quarter.

3.2.3.3 When covering the above volumes, the Technical Specifications, along with flow diagrams, logics and functional diagrams will also be reviewed where applicable.

3.2.3.4 At the end of each quarter (with the exception of the quarter in which the unit is being refueled),

the Shift Operating Supervisor will submit to the Director-Training the Operating

'Shift Quarterly Procedure Review Record (Attachment 85).

The report will detail the information covered for each member of the shift operation crew, and will contain the Shift Foreman's judgment of each operator's 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 the Control Room Inaccessibility Procedure will be conducted individually or as a group (this training is not currently available in the Simulator Training).

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Licensed Operator Requalification Program PAQK 10 15 of 3.2.3.5 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

86) at the end of each quarter.

This review will include a complete walk-through of control room inaccessibility which is conducted in the 4th quarter individually or as a group (this training is not currently available in the Simulator Training).

3.2.3.6 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. 3'7 Design changes, facilityilicense 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..

Major items will be covered in the.

preplanned lectures.

They may be accomplished

'by group or individual review and documented in the training files.

3. 2. 3.8 The staff personnel holding an NRC operator license will stand an average of four (4) hours watch in the control zoom 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, Senior Control Operator or Control Operator.

Staff members will enter their onshift time in the Control Room Time/PT Record Log Book maintained in the control room.

3.2.3.9 During all plant oper'ations, a record will be kept of any ma)or reactivity changes a licensed operator performs.

The operating shift will report these manipulations on the Reactor Operator Monthly Record (Attachment f13) or SRO Non-Staff.Monthly Record (Attachment

84) as appropriate.

Staff members will log their manipulations in the Control Room Time/PT Record Log Book.

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Licensed Operator Regnalin,cation program I

VOI PAGE 1 1 15

of 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 NRC certified individual that fails a written or oral exam wild. be removed from licensed dutie's and placed in an accelerated requalification program.

3.2.4.1 Annual Written Requalification Examination An annual written examination shall be administered to all licensed and NRC 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 89) and be used as a reference for next. requalification program.

The requalification examination willutilize the basic format of that given by the USNRC and be operationally oriented.

The passing criteria will be 80 percent overall with no category less than 70 percent.

If a licensed or NRC 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 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.

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VOI PAGK 12 15 of 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. 'n NRC type oral examination form (Attachment 82 or 82a) will be used to document these exams and the RO/SRO Oral Examination Matrix (Attachment 810) will be completed and be used as a reference for the next Oral Examination.

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 vill receive a

requalification program specifically structured to upgrade his skills and knowledge.

3. 2. 4. 3.,1 The Director-Training or his designee shall be responsible for formulating and approving the individual's accelerated progx'am.

The accelerated requalification program may involve a variety of training exercises including:

a) b)

c) d)

Directed self-study Oral interviews and discussion sessions Preplanned lectures Skills training exercise at the plant or utilizing a simulator 3.2.4.3.2 The progx'am duration vill be dictated by the extent of training required to rectify the deficiencies and the trainee's performance.

HARRIS TRAIN"<6 INSTRUCTIGNS MANU TI NO.

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Lice'..ed 0 erator R>> calificatioc Pro rae:

VOL PAGE of 13 15 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.

A.

B.

The criteria for successful completion of a written accelerated requalification exam is met by exceeding 3.2.4.1.1, or 3.2.4 '.2 as applicable'.

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.

The criteria for successful completion of an oral accelerated requalification exam is met by 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 re~ "ding the individual's permanent removal from licensed duties.

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REV-TITLE VOI PAGE t'o o ram 14 of 15 4.0 RESPONSIBILITY 4.1 The Shift Operating Supervisor 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 over-all 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 application to the NRC.

4.2.4 The proper maintenance of all records pertaining to the operator requalification program.

4.3 The Director of Nuclear

&, Simulator Training shall be responsible for the administration, evaluation, and reporting of the simulator training portion of the requalification program.

5. O ArrAcmEmS Attachments (1 through

10) listed and explained below, will constitute the documentation for the'SHNPP Operator Requalification Program.

5.1 Attachment (1)

Grade Sheet Attachment (la)

Grade Sheet Attachment (2)

Attachment, (2a)

Attachment 1 or exam section of appropriate.

R.O. Periodic/Comprehensive Exam Evaluation and S.R.O.

Periodic/Comprehensive Exam Evaluation and R.O. Oral Examination Evaluation S.R.O.

Oral Examination Evaluation la and cover sheet 2 or 2a will be placed in the the individual license personnel training folder as 5.2 Attachment (3)

Reactor Operator Monthly Record Attachment (4)

S.R.O.

(non-staff) Monthly Record Attachment (5)

Operating Shift Quarterly Procedure Review Record Attachment (6)

Staff Quarterly Procedure Review Record The Shift Operating Supervisor, will forward completed Attachments 3,

4 and 5 to the Director-Training at the required izrtervals.

Licensed staff personnel will complete Attachment jj6 and forward it to the Director-Training.

Attachment g5 and

/36 are filed in the current year folders for each of these documents.

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Ldceneed Operator Reqnaldfdcatton Program PAGE 15 15 of 5.3 Attachment (7)

Yearly Summary of Experience and Training Completed ~sing Attachments 3, 4, 5, and 6 and filed in the training summary section of the individual license personnel training folder.

5.4 Attachment (8)

Training Curriculum Development Input Vill 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..

5.5 'ttachment (9)

Requalification Matrix Attachment (10)

RO/SRO Oral Examination Matrix

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TiTLE VOL PAOK oi 1

CAROLINA POWER AND LIGHT CO>jPANY SHNPP Taken By:

Exam No.:

SECTION DATE:

TOTAL POINTS POINTS GRADE REACTOR OPERATOR EVALUATION/GRADE SHEET (PERIODIC)

(CO>jPREHENSIVE)

EXA>j 1.

Principles of Nuclear Power Plant Operation, Fluids, Thermodynamics and Heat Transfer 2.

Plant Design Including Safety and Emergency Systems 3.

Instruments and Controls 4.

Procedures

- Normal, Abnormal, Emergency, and Radiological Control Average INSTRUCTIONS 1.

Staple question sheets on top of answer sheet.

2.

Points for each question are indicated in parenthesis.

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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on a comprehensive exam.

6.

Show category and question number'ith answer (i.e., 2-1)

Provide written evaluation of.all sections for which a score of less than 70% is achieved:

(Continue on separate sheet if necessary)

Director - Training

..HARRIS TRAININIINSTRUCTIONS MANU/g Tl NO.

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CAROLINA POWER AND LIGHT COMPANY SHNPP Taken By:

Exam No.:

SECTION TOTAL POINTS POINTS GRADE SENIOR REACTOR OPERATOR EVALUATION/GRADE SHEET (PERIODIC)

(COMPREHENSIVE)

EXAM DATE:

5.'heory of Nuclear Power Plant Operation, Fluids and Thermodynamics 6.

Plant Systems:

Design, Control and Instrumentation 7.

Procedures

- Normal, Abnormal, Emergency 8.

Administrative procedures, Conditions, and Limitations Average 1

INSTRUCTIONS 1.

Staple question sheets on top of answer sheet.

2.

Points for each question are indicated in parenthesis.

I 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on a comprehensive exam.

6.

Show category and question number with answer (i.e., 3-1)

Provide written evaluation of all sections for which a score of less than 70% is achieved:

(Continue on separate sheet if necessary)

Director - Training

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Attachment 2

VOI PAGE of 1

6 CAROLINA POWER AND LIGHT COMPANY SHNPP REACTOR OPERATOR ORAL EXAMINATION CHECK SHEET CANDIDATE:

DATE:.

EXAMINER:

PASS/FAIL 1.

Understanding of Reactivity Effects a ~

b.

C ~

d.

e.

f..

go Subcritical multiplication & prediction, of critical Knowledge of when critical Instrument behavior and response Heating effects, reactivity coefficients Xe, Sm, burnup, Pu Delayed neutrons Use of facility curves, tables

& charts 2.

Instrumentation Characteristics and Design a 0 Nuclear. Instrumentation (Exco're)

(3)

(~)

(s)

(6)

(1)

Detector characteristics (source, inter., power)

(2)

Over &'nder compensation effects, discriminator Channel components and/or hardware Requirements:

startup, power, bypass Connections to safety systems

Response

to malfunctions b.

Nuclear Instrumentation (Incore)

(1)

Detector characteristics (2)

Channel components and/or-hardware (3)

Requirements (4)

Operating procedures C ~

Process Instrumentation- (Incore)

(1)

Detector location and function (2)

Recorder or. indicator location REMARKS:

N

• S Satisfactory U Unsatisfactory

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Attachment 2

PAGE 2

6 of 3.

Operating Characteristics a.

Reactor and Plant Control System (1)

Manual Operation a ~

b.

C ~

d.

Rod speed and programming Chemical shim requirements System capabilities Mechanical operation of rod drive (2)

Automatic operations a ~

b.

C ~

Conditions that must be satisfied input signals and deadband 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).

(1)

Load increase (2)

Load decrease (3)

Other (specify)

(4)

Other (specify) 4.

Facility Equipment Design and Characteristics a 0 Heat Removal Normal and. Decay (Primary Coolant

& Pressurizer, Residual Heat

Removal, Steam Dump)

(1)

Equipment location (2)

Flows, temps.,

pressures (3)

Requirements (4)

Chemistry (5)

Normal operating procedures (suggested procedures)

REMARKS:

> ~

~

'4

~

HARRIS-TRAINI G INSTRUCTIGNS MANU TI NO.

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TITLE TI-200 0

Attachment 2

VOL PAOK of 3

6 Facility Equipment Design and Characteristics (continued)

S a ~

b.

C ~

d.

e.f.

go h.

ie Cold shutdown to or from hot

'hutdown Hot shutdown to full power Boration, deboration Pressure and level control Chemical addition Other (specify)

Familiar with proper checklist Understands what he is checking Understands why he is checking it b.

Safety and Emergency (Safety Injection, Containment

Spray, Component Cooling, Emergency Boration, Pressure Relief)

C ~

(1)

Equipment location (2)

Flow paths (3)

When required (4)

Why required (5)

Initiating signals (6)

Operating procedures Auxiliaries (purification, Makeup, Seal H20, Letdown, Containment, Ventilation)

(1)

Equipment location (2)

System purpose (3)

Normal operating procedures (4)

When required (Liquid waste, solid waste, gaseous waste)

(1), Equipment location (2)

System purpose (3)

Normal operating procedures (4) 10CFR2O (Fuel handling and storage)

(1)

Personnel requirements (2)

Monitoring requirements (3).Hazards and precautions (4)

Operating procedures REMARKS:

HARRIS-TRAIN 6 )NSTRUCTIGNS MANUA 7f $0.

REV.

TITLE TI-200 0

Attachment 2

V(N PAGE of 4

6 4.

Facility Equipment Design and Characteristics (continued) d.

Electrical (1)

Normal a.

~

Sources b.

Major equipment supplied c.

Operating procedures d.

Requirements (2)

Emergency.'

~

b.

C ~

d.

e.

Sources Automatic transfer'eatures Equipment supplied Requirements Operating procedures e.

Secondary 5 e (1)

(2)

(3)

(4)

Flows, temps.,

pressures Primary to secondary leak detection Equipment function Operating procedures Periodic Tests (select at least one) a.,

Famili'ar 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 (1)

Control room identification (2)

Automatic action b.

Emergency and abnormal procedures (1)

Immediate operator action (2)

Follow-up action (3)

Notification (Plant Manager, NRC)

REMARKS:

HARRIS TRAIN G INSTRUCTIONS MANU TI 50.

REV.

TITLE TI-200 0

Attachment 2

I VOI PAGE 5

6 of 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 ~

b.

C ~

Type 'of detector Purpose Setpoint (2)

Portable a.

Radiation detected b.

Range c.

Can use the instrument b.

Characteristics (1)

Ion chamber (2)

G.. M. Tube (3)

Neutron monitor (4)

Scintillation REMARKS:

HARRlS TRAlN G INSTRUCTlGNS MANU I

VOI TI ND.

REV.

Ti-200 0

Attachment 2

TITLE PAGK 6

6 of 7.

Radiological Safety (Continued) c.

Procedures and practices (1) 10CFR20 (2)

Facility limits (3)

Facility procedures (4)

Personal practices REMARKS:

8.,

Knovledge of authorities,, responsibilities and general

.comments based'n your observation of applicant during the oral exam.

HARRIS TRAINI 8 INSTRUCTIONS MANU L I

VOL Tt NO.

TL-200 REV.

TITLE 0

Attachment 2A PAGE 1

5 of CAROLINA POWER AND LIGHT COMPANY SHNPP SENIOR REACTOR OPERATOR ORAL EXAMINATION CHECK SHEET CANDIDATE:

DATE:

EXAMINER:

PASS/FAIL Control Room a ~

b.

Shift turnover (1)

Logs and reco'rds a.

Shift supervisor b.

Operating c.

Jumper and lifted'oads d.

Surveillance e.

Tagging f.

~ Key control g.

Maintenance Control Room Reference Data (1)

Technical Specifications 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)

Comput: er (6)

Estimated critical position determination REMARKS:

• S Satisfactory U Unsatisfactory

HARRIS TRAINI G INSTRUCTIONS MANU Tl NO.

REV.

TITLE TI-200 0

Attachment 2A PAGE 2

5 of 2.

Responsibility and Authority a ~

b.

Emergency Plans (1)

Duties (2)

Types of emergencies (3)

Evaluation criteria (4)

Personnel assignments Plant Operations (1)

Startup (2)

Shutdown a.

b.

C ~

d.

Normal Automatic Outside control room Hot standby; cold shutdown c ~

Fuel Handling (1)

Storage (2)

Refueling Surveillance Testing (1) instrumentation and Control (2)

Other (Specify)

REMARKS:

'.HARRIS TRAINOII INSTRUCTIONS MANU+

Tl QO..

REV-TI-200 0

Attachment 2A PAGE'f 3.

Discussion

'a.

Transients (Specify)

(1)

Component's (2)

Instruments a.

Control room indications b.

Automatic control f

(3)

Reactor Protection a.

Automatic actions b.

Alarm setpoints (4)

Analysis a.

. Coefficient effects b.

Safety system interactions (5)

Procedures a.

b.

HARRtS TRAlN INSTRUCTlONS MANU

~

Tl f40.

RBV.

TITLE TI-200 0

Attachment 2A I

VOL PAGE of 3.

Discuss ion b.

Transients (Specify)

U" (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 O'.b.

HARRIS TRAIN 'NSTRUCT)ONS MANU

, Tl IIO.

RBV-

.TI-200 0

TITLE Attachment 2.'.

PAGE of 3.

Discussion c.

Transients (Specify)

(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.

d.

Reactivity Effects (1)

(2)

(3)

(4)

(S)

(6)

(7)

(8)

Power increases and decreases Axial and radial limits, bases Long term exposure effects Xenon oscillations Shutdown margin Dropped rod Subcritical multiplication Stuck rod e.

Thermodynamics and Hydraulics (1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

Steam tables Pressure-Temperature curves Instrumentation Pump characteristics Saturation conditions Natural circulation Water hammer Heat balance REMARKS:

.HARRIS TRAIN 8 INSTRUCTIONS MANU TI NO.

REV.

TITLE TI-200 0

Attachment 3

I VOI PAGE 1

1 of REACTOR OPERATOR MONTHLY REPORT Month:

1.

Name:

2.

Time spent on MCB hours 3.

Evolutions performed (PT's, casualties, include brief description)

A.

B.

C.,

D.

Use separate sheet for any additional evolutions performed.

4.

Number of power level changes more than 10% with rods in manual 5.

Number. of startups to point of adding heat 6.

Number of orderly shutdowns (not trips) 7.

Manual control of S/G's on plant loading 8.

Manual control of EH system du'ring plant loading 9.

Operation of manipulator during refueling 10.

Boration ll.

Dilution 12.

List ~an additional training received (courses, lectures, etc.):

A.

B.

C.

D.

E.

HARRIS TRAINING INSTRUCTIONS MANUAL

'fl NO.

REV.

TITLE TK-200 0

Attachment 4

VOL PAGE of 1

2 SRO NON STAFF MONTHLY RECORD MONTH 1.

NAME:

2.

Time spent in direct supervision of MCB.

hrs.

3.

Time spent on MCB.

~

hrs.

4.

Evolutions supervised (PT's casualties,

-etc., - include brief description (if needed)

A.

B.

C.

D.

Use a separate sheet for any additional evolutions supervised.

5.

Evolutions performed on MCB (PT's, casualties, etc., - include brief description (if needed).

A.

B.

C.

Use a separate sheet for any additional evolutions performed.

6.

Number of power level changes greater than 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 opertaion in:

C.V.

SFP hrs.

hrs.

HARRIS-TRAINING )NSTRUCTIONS MANUAL Tt MO.

REV.

TITLE Tl:-200 0

Attachment 4

VOI I

PAGE of 2

2 SRO NON STAFF MONTHLY REPORT 10.

Supervised/Operated S/G's in manual during plant startup 11.

Supervised/Operated S/G's in manual during plant startup 12.

Supervised/Operated during boration Supervised/Operated

.during boration" 13.

List any additional training received (courses, lectures, etc.)

A.

B..

C..

HARRlS TRAlN 8 INSTRUCTIONS MANU'l NO.

REV.

TITLE Tf-200 0

Attachment 5

I VaI PAGE 1

1'f OPERATING SHIFT UARTERLY PROCEDURE REVIEW RECORD QUARTER i0'ATE:

A.

Shift No.

consisting of the following personel, has reviewed the Plant Operating Manuals for this Quarter (listed below) and Technical Specifications, flov, logic and functional diagrams where applicable.

Quarter 81 (Jan. - March)

Administrative Instructions and Conduct of.Plant Operations Abnormal Procedures Emergency Instructions, Flov Charts, EPPs and FRP Quarter 83 (July Sept.)

Emergency Plan and Procedures Abnormal Procedures Emergency Instructions, Flov'Charts EPPs and FRP Quarter 82 (April June)

Precautions Limitations, and Setpoints Radiation Control and Protection Manual Abnormal Procedures Emergency Instructions, Flow Charts, EPPs and FRP Quarter 84 (Oct. - Dec.)

Fuel Follow Abnormal Procedures Emergency Instructions, Flow Charts EPPs and FRP Conduct complete walk-through of Control Room Inaccessibility Procedure l.

2.

5 ~

6..

3 ~

7.

8.

B.

With the exception of the personnel listed belov, all members of this shift are familiar with these procedures and posses the ability to take required actions as covered therein.

3 ~

2 ~

4.

• Additional Remarks:

• Remarks are required for any person listed in Section B.

Shift Foreman Operating Supervisor ROUTE TO DIRECTOR TRAINING WHEN COMPLETED.

)

'J

HARRIS TRAINING INSTRUCTIONS MANUAL TI kO.

REV.

TITLE TT-200 0

Attachment 6

VOI PAGE of 1

1 STAFF UARTERLY PROCEDURE REVIEW RECORD Period From:

To; Quarter 8

In accordance with the Plant Operating Manual, Volume I, 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 i/1 (Jan.

March)

Administrative Instructions and Conduct of Plant Operations Abnormal Procedures Emergency Instructions, Flow Charts, EPPs and FRP Quarter 83 (July - Sept.)

Emergency Plan and Procedures Abnormal Procedures Emergency Instructions, Flow Char'ts, EPPs and FRP Quarter 82 (April June' Precautions Limitations, and Setpoints Radiation Contxol and Protection Manual Abnormal Procedures Emergency Instructions, Flow Charts, EPPs and FRP Quarter 84 (Oct. - Dec.)

Fuel Follow

'bnormal Procedures Emergency Instructions, Flow Charts, EPPs and FRP Conduct complete walk-through of Control Room TnaccesslhAIilty Procedure NAME TITLE DATE ROUTE TO DIRECTOR TRAINING WHEN COMPLETED.

.'ARRIS TRAINING>

INSTRUCTIONS MANUAl TI NO.

REV.

TITLE TI-200 0

Attachment;,

7.,

I VOL PAI3E 1

1 of NPK:

YEARLY SUHHARY OF EXPERIENCE AND TRAINING.

SRO, RO, AND REPLACEIiENT CANDIDATES

'YEAR:

LICENSED HO.

DUTY HRS.

SU SD 10% P.C.

SG's EHC BOR.

DIL.

HANIP.

CRANE PT.

'",QUARTERLY CHECK-OFF.

REVIEW JAN FEB APR AUG SEPT OCT NOV DEC ADDITIONALTRAINING 2.

hours hours 3.

hours 6.

7.

9.

10.

hours hours hours hours hours hours

'hours

~

W e

t

HARRIS TRAINI 8 INSTRUCTIONS MANUAL TI NO.

REV.

TITLE TK-200 0

Attachment 8

PAGE 1

1 of 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 below 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..

c ~

2.

Transients or evolutions desired on simulator (In addition to routine requalification requirements).'

0 C ~

3.

Recommendations on items not covered under 1 or 2.

a ~

b.

C ~

Signed

.. HARRIS TRAI '

INSTRUCT!ONS MANUP' VOL a NO.

REV.

TI-200 0

-=Attachment 9

~ TITLE

'PA(Ã 1

2 of REQUALIFICATION HATRIX (OPERATOR PERFORHANCE)

Yea Sectio 19

0 ve

HARRlS'RAl '

)NSTRUCTlONS MANU

To'o.

REV.

TfTLK TI-200 0

Attachment 9

Vot-I PAGE 2

2 of REQUALIFICATION MATRIX (OVERALL EVALUATION BY SECTION)

YEAR/

EXAM TYPE RO SRO Example:

8 Passed

$P Took Average for that section

HARRIS'TRAINI G INSTRUCTIONS MANUAL TI NO; REV.

TITLE eTI-200 0

Attachment 10 VOL I

PAGE 1

.2 of R. 0.

ORAL EXAMINATIONMATRIX NAME' 1.

Reactivit Effects 2.

Instrumentation a.

N.I. (Excore b.

N.I. (Incore c.

Proc. Instru.

Incore 3.

0

. Characteristics a.

Rx.

&, Plt.

S 's.

b.

Rx.

& Plt.

Res 4.

E ui

. Desi n & Char.

a.

Heat Removal b.

Safet

& Emer.

c.

Auxiliaries d.

Electrical e.

Seconda 5.

Periodic Tests 6.

Abnormal 0 er.

a.

Alarms & Res b.

E.I.

& A.P.

c.

Emer enc Plan 7.

RADCON Safet a.

E ui ment b.

Characteristics c.

Proce.

&, Practices

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