ML17341A987

Administrative Procedure 0300, Hot License Operator Training Program.

ML17341A987
Person / Time
Site:	Turkey Point
Issue date:	11/19/1981
From:	FLORIDA POWER & LIGHT CO.
To:
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ML17341A986	List: ML17341A985 ML17341A987 ML17341A988
References
0300, 300, NUDOCS 8203300196
Download: ML17341A987 (68)

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FLORIDA POWER AND LIGHT COHPANY

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TURKEY POINT UNITS 3 AND 4 ADNINISTRATIVE PROCEDURE 0300 NOVEN8ER 19 1981 1.0 Tiel e:

HOT LICENSE OPERATOR TRAINING PROGRAM 2.0 A royal.and List of Effective Pa es:

2 1 .~A rova1:

Reviewed by Plant Nuclear Safety Committee: 81-77 and Approved by Pl ant Manager - Nuclear: 11/19/81 2.2 List of Effective Pa es:

~Pa e Date ~Pa e ~Pa e Date ~Pa e Date 1 11/19/81 10 11/19/81 19 11/19/81 28 11/19/81 2 11/19/81 11 11/19/81 20 11/19/81 29 . 11/19/81 3 11/19/81 12 11/19/81 21 11/19/81 30 11/19/81 4 11/19/81 13 11/19/81 22 11/19/81 31 -11/19/81 5 11/19/81 14 11/19/81 23 ll/19/81 32 ll/19/81 6 11/19/81 15 11/19/81 24 11/19/81 33 11/19/81 7 11/19/81 16 11/19/81 25 11/19/81 34 11/19/81 8 11/.19/81 17 11/19/81 26 11/19/81 35 11/19/81 9 11719/81 18 11/19/81 27 11/19/81 36 11/19/81 3.0 ~Sco e:

3.1 ~Per ose:

.A positive commitment to training by management will provide the most successful training processes. Written procedures and policy will provide the necessary consistency and prevent misunderstanding of goals and actions.

This procedure provides 'the instructions and guidelines for the selection, education, training, testing, and procurement of NRC Reactor or Senior Reactor Operator Licenses for the licensed control room positions on Turkey Point Units 3 and 4.

3.2 Discussion

Enthusiastic, highly qualified, fully trained, copiously proficient licensed reactor and senior reactor operators for the positions of reactor

'control operator, nuclear watch engineer, and nuclear plant. supervisor are absolutely necessary if Turkey Point Units 3 and 4 are to be operated in a safe, synergistic,. efficient and reliable manner. Upon completion of this program the successful hot license candidate will be competent in the following:

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ADMINISTRATIVE PROCEDURE 0300, PAGE 2'OT LICENSE OPERATOR TRAINING PROGRAM 3.2.1 An understanding of the fundamental principles of the disciplines which relate to his responsibilities. I 3.2.2 A knowledge of the systems, components, and instruments over which he has responsibility and control.

3.2-3 A knowl edge of appli cabl e plant .normal and emergency operating procedures, including administrative, regulatory and licensing conditions.

3.2.4 A skill in manipulation of plant controls.

3.2-5 A knowledge of plant response to various normal and casuality transients, including prevention and mitigation thereof.

The objective is to develop licensed operators who abundantly possess these above skills such that the company can realize the greatest return from its personnel, capital and plant resources.

3.3 Definitions

3.3.1 Hot License Candidate - An FPL employee who has met the screening, and seniority requirements and has been selected by the plant management to attend the hot license class and prepare him/her self for the position of licensed reactor operator (RCO).

3 3.2 Reactor 0 erator License - Authorization by the Nuclear Regulatory Commission for an individual to manipulate the controls of the nuclear facility for which he is licensed, pursuant to Title 10, Code of Federal Regulations, Part 55, "Operators'icenses".

3.3.3 Senior Reactor 0 erator License - Author ization by the Nuclear Regulatory Commission for an individual to direct the licensed activities of licensed operator or the nuclear facility for which he is licensed, pursuant to Title 10, Code. of Federal Regulations, Part 55, "Operators'icenses".

4.0 Precautions

None 5.0 Res onsibilities:

5.1 The Trainin Su ervisor's responsibilities include the following:

5.1.1 Designating the hot license training instructor .

5.1.2 Prior to the beginning of classes for a new hot license group, the training supervisor will meet with the designated hot license training instructor and review the course schedule, content, anda training material to insure that the training program reflects course that will develop competent licensed operators, satisfies current NRC regulations, and includes recent plant modifications and procedure changes.

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11/19/81 AOMINISTRATIVE PROCEOURE 0300, PAGE 3 HOT LICENSE OPERATOR TRAINING PROGRAN 5.1.3 Review and critique training progress, in particular define and provide assistance to the hot license training instructor for specific training deficiencies or student problems as observed or requested by the instructor.

5.1.4 Provide assistance to the Training Instructor in keeping cognizant of new topics and areas of emphasis for the hot license class.

5.1.5 Nake final determinations for dropping candidates from the program because of failure to meet performance standards.

5.1.6 Nake final determinations for candidates'pplication to the NRC for license examination.

5.1. 7 Nake final decisions on those candidates eligible for Senior Reactor. Operator.

5.1.8 Establish with . the assistance of the Hot License Training Instructor addi ti onal course requirements for potenti al Seni or Reactor Control Candidates.

5.1.9 At the conclusion of the preceding Hot License Class, (or when the need exists) the Training Supervisor will post job notices, schedule the screening processes, interview and select personnel for the next hot license class, based on bargaining unit contract procedures. The neober of candidates desired and approval by management ser vices, if necessary, will be the responsibility of the Plant Supervisor of Nuclear Operations based on his projected licensed personnel needs.

5.1.10 Development of training material.

5.1.11 Periodically review the hot license program and incorporate improvements.

5.2 The Hot License Trainin Instructor shall be responsible for:

5.2.1 Naintaining his NRC Senior Reactor Operator license current per the requirements of Administrative Procedure 0301, Licensed Operator Requalification Program.

5.2.2 Scheduling, coordinating and conducting all aspects of the hot license program.

5.2'3 Provide interface with other depar tments and vendor s for ful I utilization of departmental expertise for the benefit of the hot

'license group.

5.2.4 Preparation of lesson plans and presentation to class.

5.2.5 Preparation and/or evaluation of both written and oral examinations administered during the program, and review of examinations/

evaluations provided by other departments.

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 4 HOT LICENSE OPERATOR TRAINING PROGRAM 5.2.7 Maintaining required documentation for each hot license candidate.

5.2.8 Reports to the Training Supervisor concerning candidate concerns and problems and failure of candidate(s) to meet perfonnance standards.

5.2.9 Making recommendations for Reactor Operator and Senior Reactor Operator License examination applications.

5.2.10 Schedule medical exams.

5.2.11 Making application to NRC for license examinations.

5.3 The Hot License Candidate shall be responsible for:

5.3.1 Attending lectures, examinations, simulator training and on-shift training as scheduled.

5.3.2 Conducting him or herself in an alert and courteous manner, participating in class discussions and cooperating fully with the instructor and fellow class members.

5.3.3 Completing all required homework by due date.

5.3.4 Completing the hot license candidate sign-off qualification manual by the scheduled due dates.

5.3.5 Maintain an average grade of 80$ or higher on written exams.

5.3.6 Scoring 80K or higher overall on written exams and 70$ or higher on each section.

5.3.7 Meet or exceed specified performance standards.

5.3.8 Insuring the use of current controlled documents.

5.3.9 Maintain the classroom in a neat and orderly manner.

6.0

References:

6-1 10 CFR 50 62 10CFR55 6.3 ANS 3.4/ANSI N546 6.4 ANS 3-1 6.5 NUREG 1750 6.6 NUREG 0737 6.7 Institute of Nuclear .Power Operations - Guidelines for gualification Programs at Operational Units

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 5 HOT LICENSE OPERATOR TRAINING PROGRAM 6.8 Institute of Nuclear Power Operations - Nuclear Power Plant Training Personnel 6.9 Turkey Point Plant Hot License Group Seven Class Schedule 7.0 Records and Notifications:

7.1 Records of the following will be maintained by the Nuclear Training

- Department and transferred to Document Control upon acquisition of an 'NRC license by the candidate:

7.1.1 Master .copies of all written exams and answer keys (does not include quizzes) 7.1.2 Candidate's completed exams.

7.1.3 Candidate's oral evaluations.

7.1.4 Candidate's completed qualification book.

4 7.1.5 Screening results 7.1.6 Copies of the NRC license application including NRC 396 forms, Resumes, and other 10 CFR 55 requirements. (Copies of these documents also retained by g. C.)

7.1.7 Simulator training records, 8;0 Instructions:

8.1 Selection S.l.l ~lifi f

In order to meet the requirements speci i ed by the Nucl ear Regulatory Comnission and to provide the Company with competent operators, the following specific minimum requirements shall be met for selection as a Reactor Control Operator Hot License Candidate.

1~ Education must be a high school graduate or have successfully

~comp eted the general education development (GED) test.

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2. Medical must be abl e to pass the florida Power and Li ght Company Medical Exam, the NRC Form 396 medical exam and the guidelines of the current revision of ANS 3.4/ANSI N546, "Aneri can National Standard Medi cal Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants".

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 6 HOT LICENSE OPERATOR TRAINING PROGRAM

3. ~h (1) Reactor 0 erator - shall have by the conclusion of the hot license training program at least 2 years of power plant experience, 1 year of which shall be nuclear power plant experience. Experience should be evaluated on a case-by-case basis within the guidelines of. ANS 3.1 and current NRC regulations.

(2) Senior Reactor 0 erator - shall have the conclusion of tlie hot >cense course or SRO upgrade training 4 years of resposible power plant experience (a maximum of 2 years which can be fulfilled by acedemic or related technical training on a one for one basis), 2 years shall be nuclear power plant experience - 6 months of which shall be on the Turkey Point units. The SRO candidate shall also be required to have at least 1 year experience in a licensed capacity at a nuclear power plant. This 1 year license experience may be waived if the candidate is a degree holding engineer and has completed a "cold '1icense" training course as prescribed by the applicable revision of ANS 3.1.

4. ~reen~ncr The applicant will be required to take and pass a screening exam. This examination will be, administered and evaluated by an independent organization, organized for this purpose without affiliation to Florida Power and Light Company. The minimum score for passing will be determined by the Nuclear Training Supervi sor using appropri ate data from the screening organization to determine a reasonable probability of meeting the NRC examination requirements.

8.1.2 Sel ection Process Candidates will be selected through the normal bargaining unit job bidding process as illustrated in the Appendix A flow chart.

Selection will be based upon seniority of those who meet or exceed the minimum qualification requirements. In the event that an insufficient number of candidates are provided by this bidding process, a selection process '(Appendix A) will be utilized to obtain the balance of personnel required to fill the hot license class, still however, maintaining the required minimum qualifications.

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 7 HOT LICENSE OPERATOR TRAINING PROGRAM 8.1.3 NRC Reactor and Senior Reactor 0 erator License A lication Sixty days prior to the scheduled date for the NRC simulator/plant examinations, application will be made to the NRC for administering the license examinations. 10 CFR 55 specifies the material that must be included in the application. Application will be made to the NRC only for those candidates who are satisfactorily passing the course work, those who fail to satisfactorily complete. the course after application has been made, will be denied permission to sit for the NRC examinations. At the discretion of the Nuclear Training Supervisor, if a particular candidate exceeds the Reactor Operator minimum standards to such an extent that he is a viable Senior Reactor Operator candidate, and meets the additional minimum experience qualifications (8.1.1.3) he may be allowed application to the NRC for the Senior Reactor Operator license examination.

This will be provisional on his completing additional training requirersents as determined by the Training Supervisor. These additional requirements will be at a minimum, additional self study to broadening his knowledge of all aspects of theory and plant operation and passing a written and oral FPL Senior Reactor

. Operator examination.

8.2 Hot License Trainin Pro ram 8.2.1 Classroom 39 weeks Mathematics 2 weeks*

Reactor Theory 5 weeks*

Reactor Chemistry I week*

Heat Transfer and Fluid Flow 3 weeks*

Materials Science 1 week*

Health Physics 1 week*

Plant Systems 12 weeks*

Operating Procedures Training 4 weeks*

Administrative Procedures and Requirements 1/2 week*

Recent Operating experiences 1/2 week*

Mitigating Core Damage and Transient Analysis 2 weeks*

Final Review 7 weeks*

• Time allotments shown are for guidance, they may be adjusted as necessary at the discretion of the Hot License Training Instructor.

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11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 8 HOT LICENSE OPERATOR TRAINING PROGRAM 8.2.2 Simulator 6 weeks Control Room Familiarization Start-up Training Transient/Casualty Training NRC Evaluations 8.2.3 On-Shi ft Trainin 20 weeks

" On-Shift Nuclear Operator Training 3 weeks On-Shift Health Physics Phase 1 week On-Shift Turbine Operator Training 2 weeks On-Shift Control Room Training (extra person in Control Room) 14 weeks 8.3 Hot License Candidate Evaluation 8.3-1 ~izzes - Short written quizzes, usually essay type question, given periodically, usually without notice at the discretion of the i nstructor.

8.3.2 Tests Written - Comprehensive exams given at the conclusion of various segments of the course, generally at time intervals not to exceed 3 weeks. These exams will generally be constructed and graded in the NRC format.

Oral - NRC type oral examinations are to be administered to each candidate, preferably one-on-one, by the training instructor or his designee. These examinations are to be administered as frequently as possible at the discretion of the training instructor. A minimum of 6 of these examinations shall be given throughout the course.

8.3.3 FPL Final Examinations:

Written - NRC type examination written and administered by the Nuclear Training Department at the conclusion of the Training Course.

Oral - NRC type examination administered by SRO licensed personnel of the Nuclear Training Department or members of plant management currently holding SRO licenses and designated by the Nuclear Training Supervisor. These examinations are to be administered at the conclusion of the hot license training course prior to the NRC examinations.

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11/19/81 ADMINISTRATIVE PROCEDURE 0300,'AGE 9 HOT LICENSE OPERATOR TRAINING PROGRAM 8.3.4 FPL Reactor 0 erator uglification Manual The purpose of this manual is to provide the candidate with a guide for acquiring a practical knowledge of systems, theory, technical specifications, procedures and plant evolutions. Each system, procedure and evolution will require a signature from a specified license holder, all signatures shall be obtained prior to the FPL final written exam. This manual will become a permanent part of the candidates training records. This book when utilized ful.ly, will aid the candidate greatly in perfecting his operational and oral communications skills.

8.3.5 Homewor k Homework will periodically be assigned by the Training Instuctor, usually time will be available during class, however, like studying for exams, sometime maybe required outside of class for completion of homework. Tliis homework will range from short projects to NRC type essay questions and answers.

8.3e6 Simulator The candidate will be evaluated throughout simulator training by the simulator staff and the hot license training instructor. This evaluation will include the candidates knowledge of systems,

'rocedures, concepts, transients, casualties, reactor theory, heat

. transfer and fluid flow; basically the candidate will be evaluated on his ability 'to put into practice the previously learned subjects.

8.4 Performance Standards 8.4.1 Minimum Re uirements

1. ~uizzes - 80% considered passing

2. Tests Written - 8(5 overall and 70K per section considered passing Oral - Evaluation made by interviewer to be satisfactory, marginal or unsatisfactory. Marginal and satisfactory considered passing.

3. FPL Final Examinations Mritten - 80% overall and 7(5 per section considered passing Oral - Evaluation made by interviewer to be satisfactory, marginal or unsatisfactory. Marginal and satisfactory considered passing.

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 10 KOT LICENSE OPERATOR TRAINING PROGRAM

4. FPL Reactor 0 erator uglification Manual - Completion of all signatures by assigned due dates.

5.. Homework - Completion of all homework on assigned due dates.

6. Simulator - The candidate must show a proficiency in routine and casualty plant operations, procedures, plant responses, reactor theory, systems, heat transfer, and fluid flow to the

, simulator staff and/or the Nuclear Training Department representative.

7. Course Avera e - The student must maintain an overall average of 80', when a written tests (not quizzes) are averaged.

8.4.2 Failure to meet Standards

1. ~uizzes - Failure to make an 80% or higher grade on a quiz will result in a make up quiz, or additional homework in that subject as determined by the instructor.

2. Tests Written - Failure to pass a written test will result in probation, failure of two tests in a row will result in being dropped from the course. Probation at the option of the instructor wi 1 1 resul t in addi ti onal homework or make-up test(s) to aid the student in any deficiencies.

Oral - Failure to pass an oral examination will result in additional oral examinations, if after additional orals are further evaluation will given insufficient improvement is made, be made by the Nuclear Training Supervisor. This evaluation will consider the candidate's written test average, skills in oral communications, and any other material variables. The Training Supervisor has the option to drop the candidate at this point.

8.4.3 FPL Final Examinations:

Written - Failure to meet the minimum required grades will failure of the course and withdrawal of the MRC license 'onstitute application. However, in the event that a candidate has continuously met or exceeded all other performance standards he/she may be given a final make up exam in the sections with scores less than 701 and if scores of 8(5 or greater are obtained, and when

'veraged with the balance of the original exam average 80$ or greater, then the student will be considered to have passed the course and allowed to take the NRC exam. It should be noted that:

due to scheduling problems this option may be impossible and would require the candidate to re-apply to the NRC for an examination at a later date. These options are at the discretion of the Nuclear Training Supervisor and approval from the Nuclear Plant Manager, however, failure to meet the make-up exam criteria will result in being dropped from the course.

0 11/19/81 ADMINISTRATIVE PROCEDORE 0300, PAGE 11 HOT LICENSE OPERATOR TRAINING PROGRAM Oral - Failure to pass the final oral exam will require further evaTuati on by SRO member s of the Nucl ear Training Department.

Based on previous records and the combined evaluations of the interviewers a determination will be made by the Nuclear Training Supervisor, if he decides to let the student sit for the NRC examination approval must be obtained from the Nuclear Plant Manager. A negative determination by the Nuclear Training Supervisor will result in being dropped from the course.

8.4.4 FPL Reactor 0 erator uglification Manual Satisfactory completion of the RCO training course will require compl etion of al 1 signatures in the qualification manual, therefore, failure by the candidate to acquire all signatures will result in being dropped from the course. If a candidate becomes significantly behind schedule in obtaining the required signatures, and is unable to provide the training department with a reason, he will be given a two week period to show improvement. If no improvement f s shown the candidate wil 1 be dropped from the program.

8.4.5 Homework Homework is an important phase of the learning process and required as part of class, failure to do so will result in being iranediately .

dropped from the course.

8.4e6 Simulator The candidate must satisfactorily complete simulator training prior to taking the NRC simulator exam, failure to do so will result in being dropped from the course.

8.4.i ~CII A student with a written test average of less than 8(5 will be placed on probation. Failure of any two exams and an overall grade average of less than 80$ will result in an automatic drop from the course (see 8.4.2.2 Tests for probation responsibilities).

8.5 Recommended Schedule The following is a suggested outline for the sequence of presentation of course material, tests, on shift time, simulator training, NRC examinations and approximate time allocation for each. Due to problems in scheduling simulator time adjustments may be required, however, scheduling simulator time well in advance will greatly enhance the ability to schedule as desired.

MEEK 1 - Mathematics, Test No. 1 WEEK 2 - Mathematics, Test No. 2 WEEK 3 - Primary Plant Systems

11/19/81 AOMINISTRATIVE PROCEOURE 0300, PAGE 12 HOT LICENSE OPERATOR TRAINING PROGRAM MEEK 4 - Primary Plant Systems, Test No. 3 MEEK 5 - Primary Plant Systems WEEK 6 - Primary Plant Systems, Test No. 4 WEEK 7 - Primary Plant Systems, WEEK 8 Primary Plant Systems, Test No. 5 WEEK 9 - Primary Plant Systems MEEK 10 - On-Shift N. 0. Training and Oral Evaluations WEEK 11 >> On-Shift N. 0. Training and Oral Evaluations WEEK 12- On-Shift N.'. Training and Oral Evaluations MEEK 13 - Test No. 6 (N.O. Final Exam), Secondary Plant Systems WEEK 14 - Secondary Plant Systems WEEK 15 - Secondary Plant Systems WEEK 16 - On-Shift T. 0. Training and Oral Evaluations MEEK 17 - On-Shift T. 0. Training and Oral Evaluations WEEK 18 - Test No. 7 (T.O. Final Exam), Health physics MEEK 19 - On-Shift Health Physics Training MEEK 20 - Test No. 8 (H.P. Final) Materials Science WEEK 21 - Reactor Theory, Test No. 9 MEEK 22 - Reactor Theory WEEK 23 - Reactor Theory, Test No. 10 WEEK 24 - Reactor Theory WEEK 25 - Reactor Theory WEEK 26 - Test No. 11 (Reactor Theory Final), Control and Protection Systems MEEK 27 - Reactor Control and Protection Systems MEEK 28 - Reactor Control and Protection Systems, Test No. 12, Reactor Chemi stry MEEK 29 - Test No. 13 (Reactor Chemistry), Heat Transfer and Fluid Flow

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11/19/81 ADMINISTRATIVE PROCEDURE 0300& PAGE 13 HOT LICENSE OPERATOR TRAINING PROGRAM WEEK 30- Heat Transfer and Fluid Flow, Test No. 14 WEEK 31 - Heat Transfer and Fluid Flow WEEK 32- Test No. 15 (HT and FF Final), Operating Procedures and Technical Specifications MEEK 33- Operating Procedures and Technical Specifications, Test No.,16 WEEK 34- Operating Procedures 'and Technical Specifications MEEK 35 - Operating Procedures and Technical Specifications MEEK 36 - Test No. 17, Mitigating Core Damage and Transcient Analysis WEEK 37 - Mitigating Core Damage and Transcient Analysis WEEK 38 - Test No. 18, Administrative Procedures, Recent Operating Experiences WEEK 39 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 40 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 41 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 42 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator'raining Per Student MEEK 43 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 44 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 45 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 46 - On-Shift Control Room Training, Oral'valuations and 4 Meeks Simulator Training Per Student, MEEK 47 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 48 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 49 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 14 HOT LICENSE OPERATOR TRAINING PROGRAM WEEK 50 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 51 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 52 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training per Student WEEK 53- On-Shift Control Room Training, Oral Evaluations and 4 Meeks Simulator Training Per Student WEEK 54- On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 55 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student MEEK 56 - On-Shift Control Room Training, Oral Evaluations and 4 Weeks Simulator Training Per Student WEEK 57 - FINAL REVIEW MEEK 58 - FINAL REVIEW WEEK 59 - FINAL REVIEM WEEK 60 - FINAL REVIEW WEEK 61 - FINAL REVIEW WEEK 62 - FINAL REVIEW WEEK 63 - Florida power and Light Co. Mritten and Oral Final Reactor Operator Examinations WEEK 64 - Simulator Training MEEK 65 - Simulator Training and NRC Simulator Examinations WEEK 66 - Review MEEK 67 - NRC On-Site Examinations

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 15 HOT LICENSE OPERATOR TRAINING PROGRAM 8.6 Course Content 8.6.1 Classroom

1. Mathematics (1) ~To ics Whole Numbers Fractions'ecimal s

Ratio, Proportion and Variation, Percent Measurement.

Signed Numbers Metric System and Unit Conversion Scientic Notation Algebraic Expressions Algebraic Fractions Linear Equations Fractional Equations Formulas Systems of Equations .

Exponents, Powers and Roots Common Logarithms Evaluation of Log Formulas Introduction to Base e Evaluation of Natural Log Formulas Natural Logarithm Applications Linear Graphs Semi-Log Graphs Interpreting Charts and Graphs Introduction to Trigonometry Intregal and Derivative Functions and Graphs

8. 6. 2 ~ll Ih

l. ~To ics Atomic Nomenclature Neutrons Protons Electrons Nucleous Atoms Elements Compounds Molecule Atomic Number AMU Avagardro's Number Bohr Model

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11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 16 HOT LICENSE OPERATOR TRAINING PROGRAM Atomic Mass Number Atomic Height Gram Atomic Weight Gram Molecular Weight Electron Shells Isotopes Isotones Isobars Isomers Ionization Ion pairs Kinetic Energy Electron Volt Photon C Gamma IC P

Xray Alpha Curie Physics of Atoms 'I Nuclear Forces ~ 4J Coulombic Forces Mass Defect Binding Energy

, Nuclear Stability Excitation Energy Critical Energy Radioactivity 4

Radioactive Decay Atomic Concentration Physics of Neutrons Energy Classifications Prompt and Delayed Microscopic and Macroscopic Cross Sections Slowing Down Length Thermal Diffusion Length Migration Length Mean Free Path Neutron Flux I

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Moderator Properties

~ q Neutron Sources Reflectors - Absorbers Nucl ear Reactions Elastic Inelastic Radioactive Capture particle Ejection Fission

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11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 17 HOT LICENSE OPERATOR TRAINING PROGRAM Fission Process Liquid Drop Model Fission Fragments Neutron Yield Beta Decay Gamma Reactions Energy Liberated Six Factor Formula Fuels Reaction Rate Power and Power Density Depletion Rate Reactor Kinetics Reactivity f

Coef i ci ents Temperature Effects Fuel Effects Core Age Effects Pressure Effects Fission Product Poison Effects Voiding Effects Soluble Poison Effects Burnable Poison Effects Excess Multiplication Factor Subcritical Multiplication .

Inverse Count Rate Plots Subcritical Critical Super Critical Prompt Critical Delayed Neutron Fractions Generation Times Reactor Period and Startup Rate Reactor Transient Equations Reactor Transient Behavior Doppler Effects Reactor Operation Reactor Startup Reactor Shutdown Operating Limits Power Distribution and Peaking Factors Estimated Critical Conditions and Reactivity Balances Calormetrics Transients Fuel Cycles

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 18 HOT LICENSE OPERATOR TRAINING PROGRAM 8.6.3 Reactor Chemistr

~To les Introduction to Chemistry Valence Periodic Chart Compounds Radicals Molecular Weight Nole Chemical Equations Water Hydrates Solutions and Solubility Electrolyte Acids'ases Salts Reaction Rates and Equilibrium Reversibility

+drolysi s Buffer Solutions Concentration Dilution Gases Boyles Law Charles Law Ideal Gas Law Avogar do's Law of Gases Dalton's Law of Partial Pressure Solubility Ion Exchangers

'urpose Resins Types Oxidation Radiation Effects on Water Ionization Gamma Corrosion General Local i zed Gal vani c Pitting Zircalloy Radiochemisty Primary Chemistry Control and Limits Secondary Chemistry Control and Limits Sampling Techniques and Equipment Post Accident Chemistry Considerations

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 19 HOT LICENSE OPERATOR TRAINING PROGRAM 8.6.4 Heat Transfer and Fluid Flow

1. ~To $ cs Basic Properties of Fluids and Matter Dimensions and Units Proper ties Heat Work Energy Internal Energy Steam Tables Saturated Liquids Saturated Vapor Subcooled Liquid Superheated Vapor Latent Heat Sensible Heat Enthalpy guality and Void Fraction Open and Closed Systems Gas Relationships Fluid Statics Pressure Temperature Volume Pascal's Law Potential Energy Fluid Dynamics Viscosity Number

'eynolds Friction Losses Laminar Flow Turbulent Flow Flow Energy First Law of Thermodynamics General Energy Equation Bernollis Principle Venturis - Orifices NPSH Carry Over Carry Under Two Phase Flow Application Turbines Pumps Heat Exchanger s Reactor Plants

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 20 F HOT LICENSE OPERATOR TRAINING PROGRAM Heat Transfer, Conduction Connection

.Forced Natural Radiant 4 J'

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'r Change of Phase States of Matter Enthalpy Entropy ~ F Second Law of Thermodynamics Carnot Cycle Rankine Cycle 4 Efficiency F Reactor Plant Application Heat Balances $

Burn Out and Flow Instability Boiling Water Curve Critical Heat Flux DNBR Hot Channel Factors Two Phase Flow - Voids Reflux Vapor Binding Reactor Heat Transfer Limits Core Thermal Limits Fuel and Reactor Design Peaking. Factors Axial and Radial Flux Transient Effects Accident Criteria 8.6.5 Materials Science

l. ~To ics Structure of Metals properties of Metals Alloying and Alloys used in plant plant Materials Selection and Application Basis Limitations Brittle Fracture Characteristics Analysi s Charpy V-Notch Test

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11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 21 HOT LICENSE OPERATOR TRAINING PROGRAM Minimum Pressurization Temp.

RTNDT Irradiation Effects Heat-up/Cooldown Limitations Specific Plant Material Problems Fuel Densification Steam Generator Tube Denting Effects from fuel burnup L6.6 ~16 66

l. ~To $ cs Radiation and Radioactive Decay Alpha Gamma Beta Neutron Units of Measurement Roentgen Rad Rem Dose Dose Rate Methods of Detection and Measurement Dosimeters TLD Portable Instruments Bioassays Whole Body Scan Process Radiation Monitors Area Radiation Monitors Laboratory Instruments Air Sample Swipes Liquid Samples Detector Principles of Operation Detector Curve Gas Filled Detectors Scintillation Detectors Personnel Detectors Biological Effects of Radiation Internal Hazards External Hazards FPL Guidelines NRC Limits Emergency Limits

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 22 HOT LICENSE OPERATOR TRAINING PROGRAM Principles of Radiation Protecti on Methods of Reducing Exposure Time Distance Shielding Radiation Source Calculations Point Source Line Source Plane Source Contaminati on Types Airborne Parti cul ate Liquid Gaseous Loose Surface Fixed Surface Protective Clothing Respirators Decontamination Posted Areas Radiation Controlled Area Radiation Area High Radiation Area Locked High Radiation Area Hot Spot Contaminated Area Airborne Radioactivity Area Survey Maps Radiation Work Permits Radiation Exposure Report Radiation Exposure Extension Request Health Physics Manual Health Physics Procedures 867 ~P1

1. Goal s System training will provide the candidate with a knowledge of the following concepts for each of the listed systems.

Purpose Design Bases Components

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Location Characteristics Power Supplies Associated Precautions, Limitations, Setpoints and Bases System Interrelationships

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 23 HOT LICENSE OPERATOR TRAINING PROGRAM Automatic Functions Alternate Modes of Operation Associated Instrumentation, Alarms, Indications and Controls Failure Modes .

Related Modes Related Technical Specifications Normal, Off-Normal and Emergency Operating Procedures Surveillance Procedures

~T0 les Primar S stems Reactor Coolant Systems Pressurizer

'ressurizer Relief Tank Reactor Vessel, Core and Internals Reactor Coolant Pumps Steam Generators CVCS - Charging and Letdown CVCS - Makeup and Boron Control Primary Water System CVCS - Boron Recycle Lo-Head Safety Injection Hi-Head Safety Injection Passive Safety Injection Residual Heat Removal System Emergency Containment Coolers, Filters and Sprays Ventilation Systems - Containment, Au x. Building,, Control Room and Containment Purge Containment and Aux. Building Structure Containment Hydrogen Control System Spent Fuel Pit and Cooling System Component Cooling System Sampling System Heat Tracing Waste Disposal System - Liquid Waste Disposal System - Gas Waste Disposal System - Solid Primary Process Instrumentation Process Radiation Monitoring System Area Radiation Monitoring System Nitrogen Back-up Systems Breathing Air System Fuel Handling System Electrical Systems Emergency Diesel Generators

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 24 HOT LICENSE OPERATOR TRAINING PROGRAM Secondar S stems Main Steam Reheat/Extraction Steam Auxiliary Steam and Condensate Recovery Turbine, Turbine Oil, Gland Seal and Cylinder heating Systems Auxiliary Feedwater System

.Steam Dump Systems Steam Generator Blowdown System Generator and exciter, Gas and Seal Oil System Turbine Generator, Control and Logic Condensate System Feedwater System Drain and Vent Systems Turbine Plant Cooling Water System Instrument and Service Air Service Water Amertap Compressed Gas Fire Protection Secondary Process Instrumentation and Control Secondary Sampling Intake Cooling Water System Circulating Water System Intake Systems Water Treatment Plant Reactor Control and Protection Rod Control Rod Position Indication Excore Nuclear Instrumentation Incore Instrumentation Safeguards Bus Stripping and Sequencer Reactor Protection Logics Misc. Control Diagrams Misc. Protection Logics EWD's Overpressure Mitigation System RCS Level Indication and Head Vent Containment Level and Sump Level Indication Safety Valve Monitoring System Subcooled Margin Monitor Technical Support Center and Instruments Fire Monitoring Plant Data Processor Communications Systems 10 CFR 50 Appendix I Instruments Post Accident Sampling System Accident Monitoring Systems (PAMS)

'ost Safety Parameter Display System (SPDS)

Metal Impact Monitoring System

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 25 HOT LICENSE OPERATOR TRAINING PROGRAM 8.6.8 0 eratin Procedures Trainin The following procedures will give the student a knowledge of normal, off-normal and emergency procedures which relate to multiple plant systems. The student will be required to have a basic understanding of these procedures and a knowledge of:all immediate actfons:

0202.1 0208. 12 20000 20109 0202.2 0208 13 20001 20110 0204.2 0208.14 20002 20111 0205.1 1004.3 20003 20112 0205.2 1008.2 20004 20113 0208.1 1008-3 20005 20125 0208.3 1008.4 20006 20126 0208.4 1008.6 20101 20201 0208.5 1008.7 20102 0208.6 1508.2 20103 0208.7 2608.1 20104 0208.8 3208.1 20105 0208.9 4004.2 20106 0208.10 4004.4 20107 0208.11 4008.1 20108 Addi tiona1 ly the Emergency Pl ans and porti ons of Technical Specifications not previously covered will be discussed.

8.6.9 Administrative Procedures and Re uirements

~To $ cs RCO Position Description Shift Duties and Responsibilities Shfft Turnover Operating Logs Use of Procedures In-Plant Equipment Clearance Orders Jumper and Disconnected Lead Log Control of Valves, Locks and Switches Equipment Out of Service Log Instrumentation Out of Service Log Reportable Occurrences Reports required by Technical Specifications and 10 CFR Shutdown Rate Guidelines Notification of Significant Events to NRC Procedure Review, Revision and On The Spot Changes gualfty Assurance and quality Control Document guality Control Radioactive Releases Plant Modifications Interface with Division and Systems Licensed Operator Requalification Program

0 0

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 26 HOT LICENSE OPERATOR TRAINING PROGRAM

' 8.6.10 Recent erato n Ex erfences

l. ~To ics This classroom segment is designed to bring the candidate up to date on recent operating experiences and lessons learned at Turkey Point and other nuclear power plants. It also should aid the candidate with current plant operating conditions prior to his Control Room on-shift training.

8.6.11 Miti atin Core Dama e and Transient Anal sis

l. ~To $ cs Integrated Plant Transient Response Startups Shutdowns Up Power Transients Down Power Transients Runbacks Trips Rod Drops Loss of RCP's Loss of Pressurizer Spray Control Uncontrolled Boron Addition/Dilution Accidents Loss of Normal Feedwater Cooldown Accidents Load Rejections BOL, EOL Considerations Accident Analysis LOCA's Steamline Breaks Steam Generator Tube Ruptures with Steamline Breaks Multiple Steam Generator Tube Ruptures Feedwater Line Breaks Anticipated Transients without Scram (ATNS)

Natural Circulation Cooldown Inadequate Core Cooling LOCA without Safety Injection Complete Loss of Feedwater Complete loss of all A.C.

FSAR Chapter 14 Fault Trees Critical Safety Functions Incore Instrumentation for:

Determining extent of core damage and geometry changes Determining peak temperatures Print out of core data

11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 27 KOT LICENSE OPERATOR TRAINING PROGRAM Excore Data for:

Determination of voids and void location Vital Instrumentation Instrumentation response in accident environment Modes of Failure Indication Reliability .

Alternate Parameter Measuring Methods for:

I RCS parameters

'etdown Flow Pressurizer Level Primary Chemistry Expected Chemistry results with severe core damage Expected isotopic breakdown for core on clad damage Long term corrosion effects Radiation Monitoring Process and Area Monitor Response to Core Damage Use of detectors to determine extent of core damage Determination of inside containment dose rates from outside readings Gas Generation Sources Kydrogen Problems

.Oxygen Problem 8.6.12 Final Review

1. Discussion:

Review will consist of classroom instruction'ith a great deal of class participation. All previously covered topics will be reviewed with emphasis placed on selected topics as determined by the Kot License Instructor. The following methods of class participation should be used by the instructor.

Instructor Lectures gUlzzes Lectures by Students

.guestions and Answers Written by the Student Self Study and Study Teams Student Walkthru's

2. Simulator (1) Content

1. Control Room Familiarization

2. Routine Startup and Shutdown Evolutions

3. Transcient/Casualty Training:

Reactor Trips Runbacks Turbine/Generator Trips

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 28 HOT LICENSE OPERATOR TRAINING PROGRAM Feedpump Trips Failed Steam Generator Feed Regulating Valve Steam Dump Failures Loss of Condenser Vacuum Loss of Instrument Air Pressurizer Level/Pressure Control Failures Boron/Dilution Nake-up Nalfunctions Dropped Rod(s)/Control Rod Out of Alignment Control Rod Drive Failure Loss of NIS Channel Loss of Protective Channels Various Instrument Failures Emergency Boration High RCS Activity Loss of Component Cooling Reactor Coolant Pump Seal Failures Loss of RHR Loss of all (Normal and Emergency) Feedwater Loss of Coolant Flow Natural Circulation Loss of Coolant Accidents Small Leaks Large Leaks NHA Nain Steam Line Breaks

. Feedline Breaks Steam Generator Tube Ruptures Anticipated Transients without Scram (ATMS)

Multiple Failures

4. NRC Evaluations Startup Certification Casualty Drills

3. On-Shift Trainin The purpose of on-shift training is to aquaint the student with each watch 'stations duties and responsibilities, with particular emphasis on the RCO duties. These periods on shift will provide the student with time to become familiar with systems and normal and off-normal evolutions. The student will be expected to trace out systems and become experts in instrument and equipment location. The N.O. and T.O. on-shift periods are primarily intended for this purpose. The qualification sign off manual will be. extensively utilized during these periods. Reference to the qualification manual (Appendix B) will guide the student to specific evolutions and topics that will maximize familiarity and experience in on-shift operations. On-shift training will be broken into the

. following phases:

0 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 29 HOT LICENSE OPERATOR TRAINING PROGRAM On-Shift Nuclear Operator Phase:

Duties and Responsibilities of the Nuclear Operator Tracing and becoming familiar with primary systems Interfacing with RCO and Nuclear Watch Engineer Completing appropriate por tions of qualification manual On-Shift Turbine Operator Phase:

Duties and Responsibilities of the Nuclear Turbine Operator Tracing and becoming familiar with secondary systems Interfacing with RCO and Nuclear Watch Engineer Completing appropriate portions of qualification manual On-Shift Health Physics Phase

'uties and Responsibilities of the Radiation Protection Man Become proficient with the various instruments used by the RPM Complete appropriate portions of qualification manual On-Shift Control Room Phase Duties and Responsibilities of the RCO Gain a proficiency in Control Room operations Interfacing with balance of on-shift personnel, division, systems and various maintenance'epartments, other departments Complete appropriate portions of qualification manual 8.7 Course Instruction 8.7.1 Classroom The hot 'license training instructor will perform the majority of the classroom instruction, however in various topics, specialized instructors may be utilized. All instruction pertaining to plant safety systems, integrated responses, transient and simulator courses shall require the instructor to have a current SRO license. Those who teach in specialized areas such as thermodynamics, heat transfer, fluid flow, materials science, basic .

reactor theory and math, as examples, need only demonstrate compentence in their given field to the training supervisor.

8.7.2 Simul ator Instruction dur ing this phase may be provided by either the simulator facility, the Turkey Point Training Staff or both. This will be determined jointly by the Hot License Training Instructor and the Training Supervisor.

Q 11/19/81 ADMINISTRATIVE PROCEDURE 0300, PAGE 30 HOT LICENSE OPERATOR TRAINING PROGRAM

~ 8 7 3 On-Sh'Ift Trainfn The Nucl ear Pl ant Supervi sor and Nucl ear Watch Engineer are responsible for the training of personnel assigned to their shift. Students who are on-shift for training will ultimately

',report to the NPS. However, the students wil.l usually be under the direct supervision of the qualified and/or licensed operator.

Depending on the phase, the NO, RPM, NTO or RCO will be 'responsible

'Or ensuring that the student's involved actively in all occurring plant evolutions, he will additionally be responsible for training the student in operating procedures and practices as related to systems under his cognizance. The student is, of course, ultimately responsible for his training and must strive to obtain the most from his training time on-shift. Any problems or deficiencies shall be reported to the Hot License Instructor.

immediately.

8.8 NRC License Examination:

The license examination is detailed in 10 CFR 55, basically it is in four segments:

1.

3.

Startup Certification Casualty Examinations Written Examination

4. Oral Examination No candidate will be allowed to sit for the, NRC examination without satisfactorily completing all phases of the hot license training program. Successful passing of the Turkey Point hot license course is no guarantee of successfully passing the NRC examinations, therefore, some provision must be made in the event the candidate is denied a license.

lhe Training Supervisor must consider a number of things before making a recomnendation to the Nuclear Plant Manager who should make the final decision in this matter:

Desire of the candidate Performance throughout the course Attitude of candidate Evaluation by NRC of the candidate Nuclear Operations Departmental needs Nuclear Training Department ability to provide additional training If the Training Supervisor recommends to the Nuclear Plant Manager to allow the candidate to sit for another exam and he concurs, the Training Supervisor or his designee will develop a program to strengthen the candidate weaknesses. Evaluations will be made throughout the program to insure adequate progress is being made by the candidate. Re-examination will then depend on the candidates ability to pass both a written and oral comprehensive examination, and further recoeoendation by the Training Supervisor and Nuclear Plant Manager.

0 APPEND LX A APPENOIX A AP 0300 START 11/19/81 Page 31 DRTKR'A&4K uuWDER OF HOT L lCCJLSE Chl4D lDhTES QECLOIRED TR~.5VPV. YES SEEK APPROVhl cze~m ws eT. TRQCI.

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