Text

Rev 1 to Procedure 6211-ADM-2611.02, TMI-1 Senior Reactor Operator Replacement Training Program
	ML20093G126
Person / Time
Site:	Crane
Issue date:	03/21/1983
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20093G104	List: ML20093G106; ML20093G116; ML20093G118; ML20093G123; ML20093G126; ML20093G130; ML20093G135; ML20093G138;
References
	6211-ADM-2611.0, NUDOCS 8410150365
	Download: ML20093G126 (53)
	v • d • e

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Number 6211-ADM-2611.02 Revision No.

Title 1-00

I TMI-I SENIOR REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM Responsible Office Applicability / Scope TMI TRAINING DEPT.

SENIOR REPLACEMENT OPERATOR CANDIDATES This document is important to safety 0 Yes & No Effective Date March 21, 1983 Ust of Effective Pages 1.0 1-00 23.0 1-00 45.0 1-00 2.0 1-00 24.0 1-00 46.0 1-00 3.0 1-00 25.0 1-00 47.0 1-00 4.0 1-00 26.0 1-00 48.0 1-00 5.0 1-00 27.0 1-00 49.0 1-00 6.0 1-00 28.0 1-00 50.0 1-00 7.0 1-00 29.0 1-00 51.0 1-00 8.0 1-00 30.0 1-00 52.0 1-00 9.0 1-00 31.0 1-00 10.0 1-00 32.0 1-00 11.0 1-00 33.0 1-00 12.0 1-00 34.0 1-00 13.0 1-00 35.0 1-00 14.0 1-00 36.0 1-00 15.0 1-00 37.0 1-00 16.0 1-00 38.0 1-00 17.0 1-00 39.0 1-00

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Two TMI-I SENIOR REACTOR OPERATOR 1-00 REPLACEENT TRAINING PROGRAM IB TITLE: TMI-I SENIOR REACTOR OPERATOR REPLACEENT TRAINING PROGRAM 1.0 PURPOSE The purpose of the Senior Reactor Operator Replacement Training Propam is to prepare licensed reactor; operators to perfom senior reactor operator duties, improve skills in situation and problem assessment, and develop supervisory skills.

2.0 SCOPE / APPLICABILITY This procedure applies to all Senior Replacement Operator candidates designated by the Manager, Plant Operations.

3.0 DEFINITIONS 3.1 Candidate - An individual designated by the Manager, Plant. Operations

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as a potential Senior Reactor Operator.

3.2 Extra-Person - A candidate assigned to an operating shift for

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on-the-job training whose presence is not required to perfom

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specific, non-training related tasks.

3'3 a)

Task Examiner - Any qualified SRO.

b)

Alternate Task Examiner - Those individuals assigned by the Shift Supervisor in writing as being authorized to conduct a checkout on a specific OJT task and to certify by his signature on the 03T sheet that the task has been satisfactorily completed. The alternate task examiner may be any individual who the Shift Supervisor detamines through experience or personal knowledge possesses requisite knowledge of the task to properly conduct the checkout.

3.4 Instructor - A licensed or certified SRO member of the Operator Training Section of the Training Department or a " guest" instructor whose expertise in a specific subject area, e.g., a systems engineer, 3

E has resulted in his assignment, approved in writing by the Operator T

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TMI-I. SENIOR REACTOR OPERATOR 1-00 m

REPLACEENT TRAINING PROGRAM Training Manager or Manager Plant Tr'aining to present material on that subject area.

ilith the exception of guest lecturers, senior licensed or certi.fied instructors must teach systems, integrated responses and transient behavior to licensed oprators.

4.0 RESPONSIBILITIES 4.1 The Shif t Supervisor is responsibTe for the following:

a)

Assignment of individuals as alternate task examiners. ( A copy of this assignment list shall.be forwarded to the Supervisor, Licensed Operator Training.)

'b)

Designation of his shift foreman as the OJT final examiner (if j

applicable ).

(A copy of this authorization shall be forwarded to the Supervisor, Licensed Operator Training.)

c)

Verifying an adequate 1. vel of achievement and progress by the e

license candidates on the GIT phase of the program.

4.2 The Supervisor, Licensed Operator Training is responsible for the following:

a)

General supervision of the development and conduct of the

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Replacement SRO Training Program.

b)

Approval of the development, coordination, scheduling and administration of the Replacement SRO Training Program, including course outlines, lesson plans, student handouts, simulator training, and evaluation exams.

c)

Scheduling classes, students, classroom and facilities necessary to conduct the training program.

d)

Interfacing with the Operations Department in all matters impacting the training programs.

e)

Assuring that the program content is updated and revised to meet current requirements and supervising revision of the program g

2 content, descriptions, lesson plans, and exams.

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Evaluation of course instruction and license candidate progress to determine the effectiveness of the training program and reporting these evaluations to the Operator Training Manager.

g)

Maintaining the necessary records and reports cf training.

h)

Developing and conducting oral exams.

l 1)

Evaluation of candidate critiques of the training received.

4.3 The Operator Training Manager is responsible for the following:

a)

Assuring the quality of the'lieplacement SRO Training Program by written approval of materials including course outline, lesson plans, student handouts, simulator training, quizzes and exams and their compatability with the Replacement SRO Training Program.

b)

Certification of candidaQs in accordance with AP 1058.

4.4 The Manager, Plant Training ir, responsible for the following:

i a)

To ensure that the training program is developed to meet the 7

requirements established by the Director-TMI I, through the 4

Manager, Plant Operations, and that proper reccords and documentation are provided and maintained.

b)

Certification of candidates in accordanca with AP 1058.

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4.5 The Manager, Plant Operations is responsible for the following:

a)

To ensure that the overall level of training of plant operators is satisfactory through the approval of program content, schedules and administrative procedures.

b)

To evaluate candidates at the completion of the simula. tor program on their proficienccy to direct Itcensed activities.

c)

Certification of candidates in accordance with AP 1058.

4.6 The Director-TMI I is responsible for the following:

a)

Final certification of candidate in accordance with AP 1058.

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5.0 REFERENCES

5.1 American Nuclear Standard ( ANS) 3.1, Rev. 01/17/78

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5.2 Code of Federal Regulations, Section 10CFR55, Jtev. 9/1/80 i

5.3 Administrative Procedure 1058 6.0 ATTACMENTS 6.1 Appendix A '- On the Job Check 11sts

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6.2 Appendix B - Typical SRO Replacement Operator Training Schedule i

6.3 Appendix C - Candidate Progress Report & Exam Sussiary Sheets I

i 6.4 Appendix D - Simulator Training i

7.0 PROGRAM DESCRIPTION

7.1 Prerequisites

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candidates for Senior Reactor Operator shall:

1.

Have a high school diploma sr equivalency.

2.

Meet (or will meet prior to SRO License application) current Regulatory Qaide 1.8 requirements (if any) for minimum number of l

l semester hours of college icvel education in designated technical subjects.

3.

Meet the following experience requirments:

f a)

Have four years of responsible power plant experience.

Responsible power plant experience should be that obtained l

as a control room operator (fossil or nuclear) or as a power plant staff engineer involved in the day-to-day activities of the facility. A maximum of two years power plant experience may be fulfilled by academic or related l

technical training, on a one-for-one time basis. Two years shall be nuclear power plant experience.

3' b)

Three months of performing the duties of a Senior Reactor.

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Operator while under instruction as an extra person in the

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REPLACEMENT TRAINING PROGRAM i-00 c)

Have at least one year of' experience as a licensed operator at TMI-!; or.

d)

At least an R0 license or equivalent [ military experience at some other plant and at least six months in Unit I followed by a mock exam to detennine capability of completing a Unit I SRO replacement program prior to entering the program; or e)

Possess a degree in engineering or applicable sciences.

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Satisfactorily meet the minisium medical requirements for l

licensed personnel as specified in 10CFR55.

7.2 Sequence

(See Appendix 8) 1.

The program consists of the following:

a)

Classroom (approximately 14 weeks) b)

OJT - 3 monthsiRuns concurrent with classroom for 2 of the three months required. De additional month is made up before the prosram, after the program or as authorized by the Manager, Plant Operations.

c)

Decision Analysis (3 days) d)

Supervisory Development (1 week).

e)

Simulator Training (2 weeks)

The program concludes with the NRC examination.

7.3 Program mjectives:

1.

Conduct training in the subject areas Itsted below to enable the trainee to demonstrate through written and oral examinations.

completion of specified practical factors, 'and completion of an operating examination, the ability to direct the activities of licensed operators safely and competertly and to obtain an NRC f

Senior Reactor Operator license.

Subject Areas l

a)

Supervisory course in decision analysis / supervisory development.

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Supervisory control room and plant operating experience, directed by' specific task assignments and licensed senior operators.

c)

Reactor lheory d)

Plant Design and Operating Characterists e)

Plant Control Systems f) ' Radiation Control and Safety g)

Fluid Flow, Thennodynamics and Heat Transfer h)

Plant Transients 1)

Recognizing and Mitigating Core Damage j)

Sigulator Training 1.

Certify the competency of" applicants to direct the operation of the plant safely and' efficiently by satisfactory achievement of specified learning objectives, which are administrative 1y

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documented.

7.4 Outline

1.

On-the-Job Training a)

Secondary Systems b)

Pr'imary Systems c)

Administrative Procedures d)

Normal, knomal and Dnergency Operating Procedures e)

Technical Specifications I

f)

Shift Foreman Duties

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2.

Classroom Training e

The primary purpose of the classroom training is to integrate previous system knowledge with overall plant operation and operating procedures.

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a)

Reactor Theory Review Neutrons and Neutron Interactions 3

U Solving Exponential Equations Tj Multiplication Factors v

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Ties TMI-I SENIOR REACTOR OPERATOR REPLACEENT TRAINING PROGRAM 1-00 Reactor Kinetics Reactivity.

Suberitical Multiplication Neutron Sources Reactor, Period and Start Up Rate Problem Solving in Reactor Kinetics Reactivity Coefficients Flux Distribution DNB, F, F g

H Reactor Control Fuel Assemblies and Control Rods Transients and Effects on Fuel Assemblies & Control Rod Fission Product Poistns Reactor Transient Analytis Excore Nuclear Instruments Fission Product Gasses and Fission Products b)

Heat Transfer and Fluid Flow, Thermodynamics Heat Transfer Properties of Fluids Steam' Tables Core and Plant Parameters, Normal and Transient c)

General Categories Facility Incidents Deergency Plan Security Technical Specifications Administrative Procedures Emergency, Abnormal and Normal Operating Procedures, including Abnormal Transient Operating (hidelines 3

Primary and Secondary Chemistry Review Q

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Recognition and Mitigation of Consequences of Severe Core Damage,

l Change Modifications Code of Federal Regulations d)

Radiation control and Safety Radioactivity and Radiation Effects of Radiation Radiation Exposure Limits Radiation Protection Problems i

Radiation Instruments e)

Reactor Control RCS Instrument Failures Integrated Control System (ICS)

ICS Transients' 7.5 Administration 7.5.1 Program Presentation 1.

On-the-Job Training a)

The ort the-job training program consists of preselected and day to day tasks which involve participation by the Senior Reactor Operator (SRO) License candidate in Shift Foreman related.

activities designed to reinforce classroom study, maximize new learning experiences, and stimulate interest. (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per day) b)

Primary verification of OJT tasks shall be by oral checkout of the SRO licensee candidate on individual task items by a task examinar or alternate task examiner as designated in writing by the Shift Supervisor using the Summary Sheat g

i if in Appendix C.

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REPLACDENT TRAINING PROGRAM 1-00 c)

Final ~yerification shall be by oral and written checkout of task sheet sections by the Shift Supervisor (or Shift Foreman as designated in writing by the Shift Supervisor, using the Sumery Sheat in Appendix C.

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During the G)T phase the license ' candidates shall be assigned to various shifts. During this phase, the candidate shall assume Shift Foreman duties under instruction and perfonn other tasks as assigned. (Example shown in Appendix B.)

2.

Classroom Training D

a)

The classroom training shall be approximately 14 weeks, (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per day) in duration, with material presented by qualified instructors using approved lesson plans. All portions of classroom training requiring self study shall be monitored by a qualdied instructor who shall be available for individual consultation. The schedule in Appendix B allows for self study but is not reflected on the schedules.

b)

The 3R0 license candidate will be responsible for all material presented.

If a candidate misses more than one consecutive week, the Supervisor, i

i Licensed Operator Training will review thi l

situation to determine if the candidate will be

.ble to catch up with his class, and make a recomendation to the Operator Training Manager l

and the Manager. ' Plant Operations regarding I

continuation in the program.

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TM1-1 SENIOR REACTOR CPERATOR me REPLACDiENT TRAINING PROGRAM 1 00 3.

Simulator A two (2) week Simulator Program will be utilized to reinforce classroom and WT concepts and to develop an understanding of integrated pla'nt response. In the event of an excessively large cless, the SRO license candidate's will be divided into groups of suitable size for ' simulator operations, with rotation to plant operations as required.

Evolutions required during Simulator training are specified in Appendix E.

a)

Candidates for SRO will be evaluated by the s.

Manager, Plant Operations at the completion of the simuistor program on their proficienccy to direct licensed activities. This evaluation is

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part of.the certification process.

7.5.2 Evaluation Criteria 1.

On-lhe-Job Training a)

Comprehensive oral checkouts shall be administered by the task examiners for specific task sign-offs and documented by the examiner's signature.

b)

The ultimate responsibility for detemining adequate achievement by the student rests with the Shift Supervisor who shall evaluate the perfonnance of the SRO license candidate by final oral check out and/or written questioning on each task sheet, using the Oral Examination Summary Sheet in Appendix C.

This fom shall be retained in the candidate's pemanent training file.

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c)

All tasks which cannot be performed are to be f

simulated. Perfomance or simulation of a task

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d).

Individuals failing to achieve a " pass" grade on

" Final Verification" checkouts shall be:

' 1.

Infomed of their weak areas and given directio'n on the material that they should study to upg' ade their perfonnance.

r 2.

Re-examined within two weeks of the initial failure.

NOTE: Details of weak areas and scheduled date for re exan must be fomarded to the Supervisor, Licerised Operator Training.

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If an individual fails the second section check-out the Manager, Plant Operations and the Operator Training Manager shall review the 'SRO license candidate's overall progress and

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perfomance and determine the corrective action tg be taken.

2.

Written Examinations Written examinations shall be administered by representatives of the Operator Training Section on a weekly basis. Questions shall cover that material presented in the classroom, material specified for self study, and the material identified on the task sheets.

A passing grade of 805 is mandatory for all written examinations. A grade of less than 80% will require 3

candidate counselling by the instructor responsible Q

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for noted weak area (s) on the candidate's exam with suggested corrective actions that will upgrade the individual's perfomance. A re exam shall be administered within two weeks. 'If an individual fails the second exam the Manager, Plant Operations and the Operator Training Manager shall evaluate the SRO license candidate's perfomance and decide on the corrective action'to be taken.

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3.

Final Examination A comprehensive written and oral examination shall be administered by the Training Department at the conclusion of the training program. An 805 overall average and a 70% on individual sections is required for th'e satisfactory completion of the written phase.

The oral examination should nomally consist of two phases; a " walk throup" phase, administered by an Instructor desigested by the Supervisor, License-d Operator Training, and a " board" composed of Instructors designated by the Supervisor, Licensed Operator Training, and the Manager, Plant Operations or his designateil representative. A " pass" grade is required for the oral exam substantiated by documentation with the Oral Examination Sumary Sheets in Appendix C.

Upon completion of these exams, the SRO license candidate's training files and Training Department recommendations sh;.11 be forwarded to the Director -

TMI I, who shall certify the candidate for NRC examination or, ir, the case of unsatisfactory completion of the program, decide on the corrective g

2 action to be taken.

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7.6 01anges and Lesson Plan Correction '

7.6.1 The program.shall be maintained to r.eflect the following:

a)

Changes in regulatory requirements b)

Changes in applicable codes, standards and guides c)

Significant experiences at the facility d)

Significant experience throughout the industry e)

Remedial action reconnended by review / audit findings f)

Regularly scheduled participant critiques.

Changes will be incorporated per the applicable Training Departments Procedure.

7.6.2 Changes in the program content may be necessitated on an individual basis due to the following:

a) unplanned equipment failure or problems b) operational comittments c) procedural changes or deletions d) candidate qualifications and professional knowledge The request for deletion (s) of any requirements from this program shall be submitted by the Supervisor, Licensed Operator Training with concurrence from the license candidate. Approval of the requested deletions shall be made by the Operator Training Manager and the Manager, Plant Operations. When approved the deletion letter shall.

be kept in the Training Department files.

Deletions due to equipment problems or plant operational comittments shall only be approved for situations where plant conditions cannot be established within a reasonable amount of time before required certification. In no case i

shall deletions be authorized during a qualification program when required conditions are expected prior to certification.

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When deletions are requested due to prior candidate experience an assessment of the candidates knowledge and previous operating experience and qualifications shall be.

made by the Supervisor. Licensed Operator Training. By signing,the deletion 'etter, the Supervisor, Licensed Operator Training is verifying knowledge level and operating experience through oral or written examination

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and/or personal review of candidate:; records.

Any deletions to this program shall be made by the use of Deletion Letter fomat in Appendix "D".

7.7 Program Scheduling The program will normally be scheduled on an annual basis.

7.8 Records and Reports

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1.

A Training Program Administrative form shall be completed and

' submitted to the hiministrative Section for each classroor -

,s lecture or lesson by th'e instructor who presented the material.

T 2.

Current and past scnedules, lesson plans, student handouti, completed OJT task sheets, exam keys and completed exams and quizzes, both written and oral, as well as any additional pertinent qualification records shall be maintained on file in the Training Department.

3.

A copy of the Candidate Progress Report from Appendix C shall be initiated on each candidate and updated as follows:

a)

Following each week.

b)

Following the completion of simulator training.

c)

Following the final examinati'on.

The Candidate Progress Report shall be maintained at the training center. Copies of the updated report shall be submitted by the Supervisor, Licensed Operator Training to the e

y'g Manager. Plant Training and Manager, Plant Operations via the C

Operator Training Manager on a monthly basis, or more frequently I

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on a case-by. case basis if requested by any of the reviewing individuals.

7.9 Evaluation 1.

At the conclusion of each month of training the licens'e candidates will be asked to complete a training critique fom to assist in program evaluation. The completed critiques shall be reviewed by the Supervisor, Licensed Operator Training and

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fomarded, along with recome'ndations or corrective action taken to the Manager, Plant Training, via the Operator Training Manager.

2.

The Replacement SRO Training Program and its contents shall be reviewed and updated at the end of each program presentation by the instructors presenting the course and the Supervisor, Licensed Operator Training. 'He shall report the results of this review, along with recommendations or corrective action taken to

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the Manger, Plant T ainIng, via the Operator Training Manager.

During the presentation of the course no changes in course' content shall be made without prior approval of the Operator Training Manger.

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3.

Annually an internal team will be formed by the Supervisor, Licensed Operator Training to revieu the Replacement SR0 Training Program. The review team will consist of Instructo; s

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j from the Operator Training Section. The team will assess the adequacy of the program for.

Meeting new requirements Mequacy of records Quality of material and presentations Effectiveness In conducting the review, the team may use any records maintained by the T6 aining or Operations Departments to assist 3j them. These may include:

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REPLACEMENT TRAINING PROGRAM l-00 NRC Inspections QA Adits Other Adits Regulatory Changes Industry Expt rience License Candidate Critiques The review team shalT report the results to the Manager, Plant Training and the Manager, Plant Operations via the Supervisor, Licen::ed Operator Training and the Operator Training Manager.

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Tme THI-I SENIOR REACTOR (PERATOR REPLACE}ENT TRAINING PROGRAM 1-00 APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Administrative Procedures which must be read, discussed and walked through on shift.

NME:

DATE STARTED:

TASK EXAMINER DATE SIGNATURE

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1.0 Read and discuss the following Admini-strative Procedures:

1.01 Document Control 1001 1.02 Tagging 1002 1.03 Station Organization and Chain of Connand 1009 1.04 Technical Specifications Surveillance Program 1001J 1.05 Shift Relief and Log Entries 1012 1.06 Bypass and Safety Functions and Jumper Control 1013 1.07 Operator at trie Controls 1028 1.08 Conduct of Operations 1029 1.09 Record Retention 1024

'1.10 Equipment Control 1011 1.11 Equipment Control (tagging) 1037

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Forward completed Oral Examination Sumary to the Supervisor, Licensed u.sg Operator Training.

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REPLACDENT TRAINING PROGRAM 1-00 APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Emergency and Abnormal Procedures which must be read, discussed and walked through on shift.

NME:

DATE STARTED:

TASK EXAMINER DATE SIGNATURE 2.0 Walk through and discuss all Dnerge'ncy

& Abnormal Procedures:

2.01 Unanticipated Criticality 1203-10 2.02 Steam Supply System Rupture 1203-23

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2.03 OTSG Tube Rupture 1202-5 2.04 Lass.of Intermediate Cooling 1202-17

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g 2.05 Inadequate Core Cooling 1202-39 a.

Fir.d all indicar.fons mentioned.

b.

Locate all items used to verify that automatic actions have occured.

c.

Locate all controls necessary to perform all immediate manual and subsequent actions.

d.

Insure you can walk through all i

l Emergency and Abnormal Procedures and note indicators, check automatic actions, and simulate performing manual actions from memory.

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Forward completed Oral Examination Summary to the Supervisor, Licensed Operator Training.

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APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Emergency and Abnormal Procedures which must be read, discussed and walked through on shift.

i NNE:

DATE STARTED:

TASK EXAMINER DATE SIGNATURE

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3.0 Walk through and discuss all Emergency and Abnomal Procedures:

3.01 Loss of Instrument Air 1202-36 3.02 Cooldown Outside the Control Room 1202-37 3.03 Inadvertent Closure of Main Steam Isolation Yalve 1202-42 3.04 High Activity in Reactor Coolant 1202-11 3.05 Excessive Radiation Levels 1202-12 a.

Find all indications mentioned.

b.

Locate all items used to verify that automatic actions have occurred.

c.

Locate all controls necessary to perfom all immediate manual and subsequent actions.

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d.

Insure you can walk through all Emergency and Abnormal Procedure and note indicators, check auto-

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matic actions, and simulate per-l foming manual actions from memory.

'* FINAL YEkIFICATION Name/Date

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Forward completed Oral Examination Sumary to the Supervisor, Licensed I

Operator Training.

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CON MOf I Fo co'Y Nuslear s211-A0M-2811.02 Ra mon h TM1-I SENIOR REACTOR OPERATOR

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m REPLACDENT TRAINING PROGRAM l-00 APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Emergency and' Abnormal Procedures which must be read, discussed and walked through on shift.

NAlE:

DATE STARTED:

TASK EXAMINER DATE SIGNATURE 4.0 Walk through and discuss all Emergency and Abnomal Procedures:

4.01 Plant Response to Penetration of Protected Area 1202-13 4.02 Blackcut 1202-2

~

4.03 Blackout 1202-2A q

4.04 Fire,1202-31 4.05 Flood 1202-32 4.06 Earthquake 1202-30 4.07 Low System (grid) Voltage 1203-41 a.

Find all indications mentioned.

b.

Locate all items used to verify that automatic actions have occurred.

c.

Locate all controls necessary to perform all imediate manual and.

f subsequent actions.

d.

Insure you can walk through all l

Emergency and Abnomal Procedure and note indicators, check auto-j matic actions, and simulate per-l foming manual actions from memory.

l

FINAL YERIFICATION Name/Date

Forward completed Oral Examination Sumary to the Supervisor, Licensed E

Operator Training.

I g.

A0001090 3-42 240

con;nottencopy GNuclear 6211-ADM-2611.02 r flee TMI-l' SENIOR REACTOR OPERATOR REPLACENENT TRAINING PROGRAM 1-00 APPENDIX A*

ON-THE-JOB TRAINING CHECKLISTS a

This sheet lists Emergency and Abnormal Procedures which must be read, discussed and walked through on shift.

l NME:

DATE STARTED:

TASK EXAMINEit

~

DATE SIGNATURE 5.0 Walk through and discuss all Onerg'e'ncy and Abnormal Procedures:

5.01 Reactor Trip 1202-4 5.02 Turbine Trip 1202-3 5.03 Loss of RC flow /RCP trip 1202-14 5.04 Loss of Reactor Coolant Makeup 1203-15 5.05 CRD dquipment Failures 1202-8 a.

Find all indications mentioned.

b.

Locate all items used to verify that automatic actions have occurred.

c.

Locate all controls necessary to perform all imediate manual and j

subsequent actions.

i d.

Insure you can walk through all Emergency and Abnormal Procedure and note indicators, check auto-matic actions, and simulate per-forming manual actions from memory.

FINAL VERIFICATION Name/Date

Forward completed Oral E$ amination Sumary to the Su'psrvisor, Licensed g

Operator Training.

n

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ai I

l 1

2...

l 21.0

ENuslearCONiHof i FD COPY T...,m.02 h"

TMI-I SENIOR REACTOR OPERATOR Tig.

REPLACDENT TRAINING PROGRAM 1-00 APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Emergency and Abnomal Procedures which must be read, discussed and walked through on shift.

NME:

DATE STARTED:

TASK EXAMINER DATE.

SIGNATURE 6.0 Walk through and discuss all Emergency and Abnomal Procedures:

6.01 Loss of RC/RC Pressure 1202-6A e

6.02 Loss of RC/RC Pressure 1202-68 6.03 Loss of RC/RC Fressure 1202-6C.

6.04 Pressurizer Failure 1202-29 6.05 Loss'of Feed to OTSG 1202-26A 6.06 Loss of Feed to OTSG 1202-268 6.07 Load Rejection 1203-1 6.05 High Cation Conductivity in Condensate 1203-5 a.

Find all indications mentioned.

b.

Locate all items used to verify that automatic actions have occurred.

c.

Locate all controls necessary to perfom ali issnediate manual and subsequent actions.

d.

Insure you can walk through all Emergency and Abnonnal Procedure and note indicators, check auto-i matic actions, and simulate per-foming manual actions from memory.

g f.

FINAL VERIFICATION Name/Date 3-a E

Forward completed Oral Examination Sununary to the Supervisor, LicenseQ I

Operator Training.

g.

A0001000 3 82 22.0

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NuclearCON 180f I FO CO"Y 6211-ADM-2611.02

^

h" Ties TMI-I-SENIOR REACTOR OPERATOR REPLACDENT TRAINING PROGRAM l-00

~

APPENDIX A-ON-THE-JOB TRAINING CHECKLISTS This sheet lists Emergency and'Abnomal Procedures which must be read, discussed and walked through on shift.

4 NME:

DATE STARTED:

TASK EXAMINER DATE SIGNATURE 7.0 Walk through and discuss all Emergency and Abnormal Procedures:

7.01 Loss of Decay Heat Removal 1202-35 7.02 SSCC System Failure 1203-21 7.03 Control Room MVAC 1203-24 7.04 Vibration and Locse Parts 1203-40 7.05 Rive'r Water Failure 1203.-

7.06 NSCC System Failure 1203-20 7.07 RC Pump & Motor Malfunctions 1203-16 a.

Find all indications mentioned.

b.

Locate all items used to verify that automatic actions have occurred.

c.

Locate all controls necessary to perfom all immediate manual and i

a subsequent actions.

d.

Insure you can walk through all Emergency and.%bnomal Procedure l

and note indicators, check au'.o-matic actions, and simulate per-forming manual actions from memory.

FINAL VERIFICATION g

Name/Date n

Forward completed Oral Examination Sumary to the Supervisor, Licensed Operator Training.

t l

1 1

23.0 l

ENuclearCON180 i FD COPY T.,..m1.of Rm h Tme TMI-! SENIOR REACTOR OPERATOR

~

REPLACEENT TRAINING PROGRAM 1 00 APPENDIX A 03T CHECKLIST Perform the following evolutions Candidates Signature Upon and attach completed reading sheets:

Completion 1.

Take A0 Outbbilding Readings For all shifts (7-3)

(3-11)

-(11-7)

I 2.

Take A0' Primary Plant Readings For all shifts (7-3)

(3-11)

(11-7)

(

3.

Take A0 Secondary Plant Readings For all shifts (7-3)

(3-11 )

(11->7)

O I

2 1

I I

g A0001090 2-82 24.0

._m.._._,-_

2 Nuslear';ON MOf I PU boFY 1

6211-ADM-2611.02 1

Time TMI-I SENIOR REACTOR OPERATOR R9h REPLACEENT TRAINING PROGRAM 1-00 APPENDIX A-SHIFT FOREMAN TRAINEE DUTIES CHECKL.LST 51gnature (SF/SS) i 1.

Conduct shift relief as a shift foreman.

l 2.

Make a left hand log entry in accordance with 'AP 1012.

3.

Review one complete set of operator reading sheets.

4.

Demonstate proper handling of a Chemical Deviation Sheet.

l 5.

Demonstrate proper handling of Tech Spec surveillance data and schedules.

6.

Demonstate proper handling of ops surveillance data and scheduling.

7.

Demonstrate proper handling of ISI data in the alert range.

8.-

Demonstrate correct handling of work request l

(completion / initiation).

9.

bemonstrate proper handling o'f QA hold point stamps.

10. Make the proper log and checklist entries necessary to complete a valve lineup change without a TCN.

l

11. Audit the TCN and STP books.

l

13. Properly issue a jumper or lifted lead.

l

13. Demonstrate knowledge of all comunication systems including NRC phones NAWAS lines, and emergency planning phones.

14. Demonstrate proper method of recall of plant personnel including use of record-a-phone.

i

15. Properly approve and discuss testing requirements for I

ESAS component tag outs.

n

16. Conduct a crew turnover briefing.

,s g I

17. Demonstrate knowledge of duties of members on the I

fire brigade.

~

g A0001090 3 42 25.0 k

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NuclearCON1ROf i FD COPY 7.,,.2m.o, TMI-1. SENIOR REACTOR OPERATOR Rensson No.

. O-m REPLACEMENT TRAINING PROGRAM 140 APPENDIX B TYPICAL REPLACEENT SRO TRAINING SCliEDULE EEK 1 I

MONDAY l

TUE5 DAY l

WEDNE5 DAY THUR5 DAY l

FRIDAY I

0700 1 I

I I

l l

REACTOR I

REACTOR I l

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l I

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i 11.2.01.025 l 11.2.01.123 l

l l

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l l

l I 11.2.01.058 1 11.2.01.133 I

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I l 11.2.01.075 l i 11.2.01.076 l l

1 1

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REPLACEMENT TRAINING PROGRAM 1-00 1

l APPENDIX 8 l

l

' TYPICAL REPLACEMENT SRO TRAINING SCHEDULE l

WEEK 2 MONDAY I

TUESDAY I

WEDNE5 DAY l

THUR5 DAY I

FRIDAY l

0700 l

l l

1 1

l l

I I

l l

l PEACTOR l

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REACTOR 1

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l 11.2.01.129 l 11.2.01.131 l

1.1.2.01.130 I

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l WEEKS I

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l l

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CON 180f i FD COPY 2 Nuslear s211-40M-2811.02 8" "

Title TMI-I SENIOR REACTOR OPERATOR 1-00 REPLACEMENT TRAINING PROGRAM APPENDIX B TYPICAL REPLACEMENT SRO TRAINING SCHEDULE WEEK 3 l

MONDAY l

TUE5 DAY l

WEDNE5 DAY THUR5 DAY F RIDAY l

1 0700 1

l l

u l

i I

I I

I l C0siTROL ROD l CONTROL ROD l TECH SPECS l REACTOR l WEEKLY l

1 DRIVE I DRIVE i - DEFINITIONS l PROTECTION I TEST l

I i

1 - SAFETY LIMITS l SYSTEM l

l l 11.2.01.013 l

1 - LIMITING l

l l

1

. SAFETY SYS.

I 11.2.01.132 l

l l

SETTINGS i

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TYPICAL REPLACEMENT SRO TRAINING SCHEDULE

~

WEEK 4 MONDAY TUE5 DAY WEDNE5 DAY l

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0700 i

i l

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i 11.2.01.120 1 11.2.01.119 l - 10CFR55 1

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WEEK 5 MONDAY TUE5 DAY l

WEDNESDAY l

THUR5 DAY I

FRIDAY 0700 l

l

~ l i

L l

l i

l l INCORE INSTR.

I WEEKLY l

l LIQUID &

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l GASEOUS l INDUSTRIAL I

l -SPND l

l l RELEASES l WASTE SYSTEM i 3.1.12 1 -FQ,AH l

l l

I I

3.2 l -30 PWR MAP l

l l 11.2.01.059 l 11.2.01.052 l

L3 l -PHYSICS l

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Tine THI-I SENIOR REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM 1-00 APPENDIX B TYPICAL REPLACEMENT SRO TRAINING SCHEDULE

~

WEEK 6 TUE5 DAY I

WEDNESDAY l

THUR5 DAY FRIDAY l

I MONDAY I

0700 1 I

I WEEKLY

~l TECH SPECS 1 FUEL HANDLING ll EMERGENCY I RADIATION l

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I 4.7 l *-W. Cotters l

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l l Table 4.1.2 l

Book l 11.2.01.027 l

l 1

1 (items 142) I i 11.2.01.022 1 11.2.01.118 I

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THUR5 DAY FRIDAY l

0700 l

i i

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l CORE DAMAGE l CORE DAMAGE l

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11.2.01.080 1 11.2.01.072 l MON RESP.

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l l

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l 1 QUAL CARD l - LUBE OIL 1 1

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Me TMI-! SENIOR REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM 1-00 APPENDIX B TYPICAL REPLACEMENT SRO TRAINING SCHEDULE WEEK 8 1

l MONDAY TUE5 DAY WEDNE5 DAY THUR5 DAY FRIDAY l

I i

i 0700 l

.l HEAT TRANSFER l PUlf THEORY &

1 TECH SPECS l WEEKLY TEST l

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1 CHEMISTRY l

1 & FLUID l FLUID FLOW l is l

l 1 -GUIDE l DYNAMICS I

l l

l l -PRIMARY l

l I 3.7 3.9 3.10 l l

l -SECONDARY l 11,2.01.049 l 11.2.01.114 1 3.14 thru 3.17 l l

1 -REACTIONS I

I 11.2.01.115 1 3.18.1 thru I

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i i MNuslearC@lROf i FD COPY

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Title THI-I' SENIOR RF ACTOR OPERATOR REPLACEMENT TRalNING PROGRAM 1-00 APPENDIX B j

TYPICAL REPLACEENT SRO TRAINING SCHEDULE i

~

WEEK 9 l

MONDAY TUESDAY l

WEDNESDAY l

THURSDAY FRIDAY l

0700 l l

l l

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RCS ELEY l RADWASTE I SOLID PLANT l WEEKLY I

l l AND MAN 0ETER l EVAPS 1 OPS l TEST l

l l EFFECTS I

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Time TMI-I' SENIOR REACTOR OPERATOR REPLACD4ENT TRAINING PROGRAM 1-00 APPENDIX B TYPICAL REPLACEMENT SRO TRAINING SCHEDULE WEEK 10 1

I MONDAY TUESDAY l

WEDNESDAY l

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3700 I l

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l TECH SPECS I VITAL POWER I CO WUTER l MAKEUP &

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l 3.21.1 3.21.21 I

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Title TMI-I SENIOR REACTOR OPERATOR REPLACEENT TRAINING PROGRAM 1-00 APPENDIX 8 TYPICAL REPLACEMENT SRO TRAINING SC,HEDULE WEEK 11 i

l l

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g REPLACEMENT TRAINING PROGRAM 1-00

. APPENDIX C.

1.

Candidate Progress Report Name Employee No.

SSN 2.

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Pass / Fail-Date Mgr., Plant Operations 4.

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Date Supv., Licensed Oper. Trng.

5.

FINAL EXAMINATIONS Written pass / fail Oral -

pass / fail Date Date Section Results Board Members 6.

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Operator Training Manager I

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SUMMARY

SHEET Candidate:

Examiner:

Date

Purpose:

( ) OJT Section Final Verification

( ) Final Examination Grade: ( Pass / Fail )

( ) Other Sumary of Questions Asked:

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Overall Evaluation: ( Pass / Fail )

Further Action Required (if none, so state)

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Reviewed by:

Signature of Exa.niner*

Supv., Licensed Oper. Trng.

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Forward completed summary to Supervisor, Licensed Operator Training.

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Title TMI-I SENIOR REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM 1-00 APPENDIX C DESIGNATION OF ALTERNATE TASK EXAMINERS hu The below listed individuals are hereby designated as alternate task examiners for the OJT phases of the Replacement SRO Training Program for Shift

, Letter)

(

l TASK l NAME I TASK l NAME I TASK l NAME I

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Ties TMI-I SENIOR REACTOR OPERATOR 1 00 REPLACEMENT TRAINING PROGRAM APPENDIX C DESIGNATION OF FOREMAN AS FINAL alt EXAMINER DATE:

, are hireby designated to serve as the Sh1tt Sh1f t foreman final verification examiner for Replacement SRO's on shift for the Letter alt sections noted below:

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TMI-I SENIOR REACTOR OPERATOR REPLACEENT TRAINING PROGRAM 1-00 Appendix D Deletion Letter to Sedior Reactor Operator Triining Program i

Date:

l

Subject:

Deletion of Training Program Requirements for Replacement Senior Reactor Operator

~~

To: Manager, Plant Operations Operator Training Manager Ref:

(a)

Applicable section of training program i

In accordance with reference (a) ft is requested that the following requirements be deleted from the Senior Reactor 0perator Replacement Training

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(Candidates Name)

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Tide TMI-I SENIOR REACTOR OPERATOR REPLACDENT TRAINING PROGRAM l-00 Wen approved, the candidate shall mark each affected item " Deleted per 6211- (Letter Number)." A copy of this letter shall be' kept by the candidate x

cnd this letter filed in the candidates training record in the Training Department.

Submitted

,, Supervisor Licensed Ofsrator Trng.

s Concurred License candidate Approved Operator Training Manager Approved '

Manager. Plant Operations 1

Distribution:

Candidate l

Candidates Training Records.

Manager Plant Operations Operator Training Manager Supervisor Licensed Operator Training e

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Renmo h Time TMI-1 SENIOR REACTOR (PERATOR REPLACEMENT TRAINING PROGRAM 1-00 APPENDIX "D" SIMULATOR TRAINING A nuclear plant simulator provides a means of training individuals to control the plant during routine conditions and to cope with nuclear plant transients and accidents. This training should prepare the candidate to supervise proficiently routine evolutions and carryout abnonnal/ emergency actions for

.the control room. Candidates shall practice manipulating the controls of an ap;ilicable simulator as described in reference 5.6.

As a minimum the license candidate shall participate in training sessions that include those listed below. The simulator training should emphasize the senior reactor operator's role in transient and accident response.

The following control manipulations and plant evolutions are required.

Those control manipulations which cannot be perfemed at the plant shall be perfomed on a simulator.

(1)

Plant or reactor'startups to include a range that reactivity feedback from nuclear heat addition is noticable and heatup rate is established.

(2)

Plant shutdown.

(3)

Manual control of steam generators or feedwater, or both, dtging startup and shutdown.

(4)

Any s.ignificant (10 percent) power changes due to manual changes in control rod position or recirculation flow.

(5)

Loss of coolant includingi (a)

.Significant steam generator tube leaks

~

(b)

Inside and outside primary containment (c)

Large and small, including leak determination (d)

Saturated reactor coolant response (6)

Loss of core coolant flow / natural circulation.

(7)

Loss of all feedwater (normal and emergency).-

(8)

Boratie or dilution, or both during power operation.

., ".(9)

Any reactor power change of 10 percent or greater where load change is performed with load limit control.

(10) Loss of instrument air (if simulated plant specific).

(11) Loss of electrical power (or degraded power sources, or both)

(12) Loss of condenser vacuum.

(13) Loss of service water if rcquired for safety.

(14) Loss of shutdown cooling.

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(15) Loss of component cooling system or cooling to an individual component.

g (16) Loss of protective system channel.

o; (17) Mispositioned control rod or rods (or rod drops).

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j (18) Inability to drive control rod.

(19) Condition requiring.use of emergency boration or standby liquid control system.

(20) Fuel cladding failure or high activity in reactor coolant of off i

gas.

(21) Turbine or generator trip.

(22) Loss of nomal feedwater or normal feedwater system failure.

(23) Malfunction of automatic control system (s) which affect reactiv,ity.*

(24) Malfunction of reactor coolant pressure / volume control system.

(25) Reactor trip.

(26) Main steam line break (inside or outside containment).

(27) helear instrument failure (s).

Participation at simulator shall be in groups of no more than four (4) people manipulating the controls or directing the activities of individuals during plant exen:ises.

An examination using the simulator shal.1 be conducted while at operating power with plant malfunctions while starting up the reactor. The certification examination shall demonstrate the candidates ability to:

(1 )

Manipulate the controls in a safe and competent manner.

(2)

Predict instrument response and use instrumentation available.

(3)

Follow the facility proced" es, and i

(4)

Understand alams and annt. cators and take proper actions, and (5)

Communicate properly and eiiectively.

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Contents

Text

5.0 REFERENCES

7.1 Prerequisites

7.2 Sequence

7.4 Outline

SUMMARY

Purpose:

Subject:

Navigation menu

ML20093G126

Text

5.0 REFERENCES

7.1 Prerequisites

7.2 Sequence

7.4 Outline

SUMMARY

Purpose:

Subject:

Navigation menu

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