ML20041B060

To Licensed Reactor Operator Replacement Training

ML20041B060
Person / Time
Site:	05000000, Haddam Neck
Issue date:	07/23/1980
From:	Ferguson J CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20041B057	List: ML20041B060 ML20041B062 ML20041B064 ML20041B066 ML20041B069 ML20041B070
References
TASK-1.A.2.1, TASK-2.B.4, TASK-TM OP-RO-R03, OP-RO-R3, TAC-44175, TAC-44525, NUDOCS 8202230221
Download: ML20041B060 (10)

Text

m CONNECTICUT YANKEE program 1.o.,

O,_RO Rev. 3 TRAINING ABSTRACT

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s Date U 7 3%.M TITLE Licensed Reactor Operator Replacemen*, Training DEVELOPED FOR Reactor Operator License Candidates OBJECTIVE Prepare the trainee for the Nuclear Regulatory Commission Licenst Exam.

Also prepare trainee for position of Control Operator.

LENGTH 42 weeks SCHEDULE As needed TYPE Lecture /On Job Training / simulator EVALUATION Oral / written CONTENT LECTURE j

l 1.0 Introduction 2.0 Administrative 3.0 Facility Description and Operation 1

4.0 Nuclear Theory and Reactor Operation 5.0 Chemistry l

6.0 Radiation Protection ON JOB TRAINING l

l 1.0 Power Plant Experinece 2.0 Operating Experience 3.0 Control Man'ipulations SIMULATOR EVALUATION 8202230221 800815 PDR ADOCK 05000213 V

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l CONNECTICUT YANKEE greSram 1.o.,

or-Ro Rev. 3 TRAINING PROGRAM averoved: \\ int 1E' riot

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,4% ~B6 TITLE Licensed Reactor operator Replacement Training OBJECTIVE Prepare the trainee for the Nuclear Regulatory Commission License Exam.

Also prepare trainee for position of Control operator.

EVALUATION oral / written CONTENT LECTURES 1.0 Introduction 1.1 Course outline 1.2 Issue Class Materials 2.0 Administrative f

2.1 Facility Licenses 2.2 Code of Federal Regulations Title 10 2.3 FDSA Section 12 2.4, Technical Specifications 2.4.1 Appendix A 2.4.2 Appendix B 2.5 Procedures 2.5.1 Administrative 2.5.2 Quality Assurance 2.5.3 Special Nuclear Material 2.5.4 Normal operating 2.5.5 Annunciator 2.5.6 Emergency a

2.6 Emergency Plan 2.6.1 Conn. Yankee Plan 2.6.2 State Plan I

2.6.3 Emergency Plan Procedures l

2.7 TMI Lessons Learned 2.8 Security 2.8.1 Plant Access 2.8.2 Vital Area Control 3.0 Facility Description and Operation 3.1 Introduction 3.2 Site 3.2.1 General 3.2.2 Meterology and Climatology 3.2.3 Hydrology 3.2.4 Geology 3.2.5 Seismology 3.2.6 Environmental Monitoring Program 3.2.7 River Water Study 3.2.8 Facilities 3.3 Containment l

3.3.1 General i

3.3.2 Design Criteria 3.3.3 Design Description 3.3.4 Penetrations 3.3.5 Testing 3.3.6 Containment Systems 3.3.7 Shielding 3.4 Reactor Core Design 3.4.1 Mechanical 3.4.2 Nuclear 3.4.3 Thermal and Hydraulic 3.4.4 Fuel Handling and Storage l

3.4.5 Nuclear Instrumentation 1

3.4.6 Incore Instrumentation 3.4.7 Reactor Control and Protection 3.4.8 Rod Control I

3.5 Reactor Coolant System I

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l 3.5.1 Reactor Vessel 3.5.2 Reactor Coolant Pumps 3.5.3 Steam Generators 3.5.4 Loop Valves and Piping 3.5.5 Pressurizer 3.6 Chemical and Volume Control System 3.6.1 General 3.6.2 volume control Tank 3.6.3 Letdown 3.6.4 Charging 3.6.5 Seal Water Supply J

3.6.6 Drain Fill System 3.6.7 Purification 3.6.8 Chemical Addition

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3.6.9 Sampling

s 3.6.10 Vents and Drains

3. 'i Auxiliary Cooling Systems 3.7.1 General 3.7.2 Component Cooling 3.7.3 Residual Heat Removal 3.7.4 Spent Fuel Pit Cooling 3.7.5 Emergency Core Cooling 3.8 Boron Recovery and Waste Disposal 3.8.1 General-3.8.2 Boron Recovery 3.8.3 Liquid Waste Handling 3.8.4 Solid Waste Handling 3.8.5 Cas Waste Handling 3.9 Secondary Systems 3.9.2 Auxiliary Steam 3.9.3 Condensate and Feed 3.9.4 Circulating Water 3.9.5 Service Water 3.9.6 Vents and Drains 3.9.7 Water Treatment 3.9.8 Compressed Air 3.9.9 Fire Protection 3.9.10 Ventilation 3.10 Turbine 3.10.1 General 3.10.2 Mechanical Description 3.10.3 Control Oil System 3.10.4 Lubricating 011 System 3.11 Electrical l

3.11.1 Basic Electricity 3.11.2 Generator and 345 KV 3.11.3 115 KV System l

3.11.4 4160 Volt System 3.11.5 430 Volt System 3.11.6 Vital and Semi Vital Bus 3.11.7 Emergency Generators 3.11.8 125 Volt DC 3.11.9 Rod Drive Power 3.11.10 Security Power Supply 3.12 Accident Analysis 3.12.1 General (include CY specific) 3.12.2 Reactivity Incidents 3.12.3 Mechanical Incidents 3.12.4 Hypothetical Accident 3.12.5 TMI Scenario

e 4.0 Nucitar Trier >ry and Reactor Operation 4.1 Muth 4.1.1 Calculator 4.1.2 Basic Math 4.1.3 Logs 4.1.4 Power Problems 4.1.5 Units and Conversions 4.2 Basic Physics 4.2.1 Fluid Flow and Pump Theory 4.2.2 Thermodynamics 4.3 Basic Nuclear Physicc 4.3.1 Basic Physics 4.3.2 Atomic Structure 4.3.3 Physical Chemistry 4.3.4 Mass, Energy and Nuclear Stability 4.3.5 Nuclear Reactions i

4.3.6 Neutron Behavior 4.3.7 Nuclear Fission 4.4 Reactor Theory 4.4.1 Introduction and Reactor Classification 4.4.2 Neutron Production 4.4.3 Six Factor Formula 4.4.4 Reactivity 4.4.5 Control Rods 4.4.6 Neutron Sources 4.4.7 Neutron Multiplication in a Suberitical Reactor 4.4.8 Reactor Period /Startup Rate and Power Level 4.4.9 Neutron Lifetime 4.4.10 Inhour Equation 4.4.12 Time Dependence and Fission Products 4.4.13 Reactivity Balance 4.5 Core Performance and Operation 4.5.1 Heat Transfer Fundamentals 4.5.2 Heat Transfer in a Core 4.5.3 Core Loading / Refueling 4.5.4 Physics Testing 4,5.5 Power Escalation 4.5.6 Steady State Power Operation 4.5.7 Plant Transients 4.5.8 Power Distribution / Axial Offset 4.5.9 Operation with Damaged Core

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5.0 Chemistry 5.1 Basic Chemistry 5.2 Corrosion 5.3 Sources of Radioactivity in Reactor Coolant 5.4 Radiolytic Decomposition of Water 5.5 Demineralizers 5.6 Primary Coolant Chemistry Program 5.7 Secondary System Chemistry Program 6.0 Radiation Protection 6.1 Radioactivity 6.2 Radioactive Decay 6.3 Interaction of Charged Particle with Matter 6.4 Interaction of Gamma Rays with Matter 6.5 Shielding 6.6 Radiation Monitoring System 6.7 Standards and Limits 6.8 Radiation Control and Protection

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ON JOB TRAINING 1.0 Power Plant Experience 1.1 As a minimum an applicant must have six months experience at Connecticut Yankee at the time of the NRC Exam.

1.2 Applicants must meet the requirements of ANSI /ANS-3.1 (Latest Revision).

2.0 Operating Experience 2.1 As a minimum an applicant must have th'ree months of control room training as an extra person on shift.

3.0 Control Manipulations 3.1 As a minimum an applicant must have five significant reactivity changes in any combination of the following.

3.1.1 Reactor start-up to the point of adding head.

3.1.2 Orderly shutdown.

3.1.3 Manual control of steam generator level during a start-up or' shutdown.

3.1.4 Control of turbine generator during a load change of greater than 10 percent.

3.1.5 Boration during power operation.

3.1.6 Dilution during power operation.

3.1.7 Control rod manipulation during power change greater than 10 percent.

3.1.8 Control rod manipulation prior to and during generator phasing.

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SIMULATOR 1.0 As a minimum an applicant must successfuliy complete one week at an NRC approved simulator.

f 2.0 The simulator manager must certify the applicant's ability to:

2.1 Manipulate the controls and maintain control of the reactor during a reactor start-up.

2.2 Pre' dict instrument response and use the instrumentation during a reactor start-up.

2.3 Follow facility start-up procedure.

2.4 Explain alarms and annunciators that may-occur during start-up.

1 3.0 The simulator must reproduce the general operating characteristics of Connecticut Yankee.

4.0 The simulator instrumentation and controls must be arranged similar to Connecticut Yankee.

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o EVALUATION 1.0 Quizzes will be given regularly to evaluate the trainees progress.

2.0 At the conclusion of the program an NRC type exam will be adminstered each trainee.

3.0 At the conclusion of the program, an oral examination (walk through) will be administered each trainee.

4.0 Based on the results of the above evaluations and the simulator evaluation, the training supervisor will submit a recommendation to the Station Superintendent that the trainee either be certified or denied certification according to 10 CFR 55.10 (a)(6).

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