ML13308B824

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Shift Technical Advisor Training & Requalification Program
ML13308B824
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 12/31/1980
From:
Southern California Edison Co
To:
Shared Package
ML13308B823 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM NUDOCS 8101060523
Download: ML13308B824 (31)
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Text

SAN ONOFRE NULCEAR GENERATING STATION SHIFT TECHNICAL ADVISOR TRAINING AND REQUALIFICATION PROGRAM

DECEMBER, 1980 ENCLOSURE 801060 Sg 3

TABLE OF CONTENTS Title Page No.

Introduction 4

Qualifications 4

Area I -

General Technical Education 4

Area II -

Reactor Operations Training 5

Area III - Transient and Accident Response 5

Training Examinations 6

Requalification Program 6

Documentation 6

Appendix A - Administrative Training 8

Appendix B - Engineering Mathematics 9

Appendix C - Heat Transfer and Thermodynamics 11 Appendix D - Chemistry and Radiochemistry 12 Appendix E - Material Strength and Properties 13 Appendix F - Reactor Physics and Reactor 14 Control Appendix G - Fluid Mechanics 15 Appendix H - Electrical Engineering 16 Appendix I - Administrative Orders, 17 Regulatory Controls and Plant Procedures Appendix J - Nuclear Steam Supply Systems 18 Appendix K -

Balance of Plant Systems 20

Title Page No.

Appendix L -

Instrumentation System 21 Appendix M - Transient Analysis 22 Appendix N - Accident Analysis 25 Appendix 0 - Nuclear Plant Simulator 26 Appendix P - Requalification Program 28

STA TRAINING AND REQUALIFICATION PROGRAM Page 4 SAN ONOFRE NUCLEAR GENERATING STATION SHIFT TECHNICAL ADVISOR TRAINING AND REQUALIFICATION PROGRAM INTRODUCTION The purpose of the Shift Technical Advisor Initial Training program is to supply, on shift, an individual with both extensive academic training in applicable engineering and science and practical power plant experience and training.

These requirements are coupled with further training in expected plant transients and accident analysis.

INITIAL QUALIFICATION OF CANDIDATES Candidates for the position of Shift Technical Adivsor (STA) will possess a bachelor's degree or equivalent in a science or engineer ing discipline prior to entering the program.

PROGRAM Shift Technical Advisor Initial Training will be of approximately thirty (38) weeks duration and is divided into three (3) general areas as follows:

Area I - General Technical Education The main objective of training in this area is to supplement the STA candidates technical education, as required, to achieve the equiva lent of sixty (60) semester hours of college level instruction in eight (8) nuclear plant related subjects.

A second objective is to provide plant specific and review training in these same subjects which will be integrated, to the extent possible, with any supplemental training required.

The eight (8) subjects are listed below:

Engineering Mathematics Heat Transfer and Thermodynamics Chemistry and Radiochemistry Material Strength and Properties Reactor Physics Combined Subjects Reactor Control Fluid Mechanics Electrical Engineering Upon entering the STA Training Program, the STA candidates college transcripts or other certification will be reviewed and a curriculum developed to cover required subject matter not documented.

In this case sixteen (16) hours of instruction, including review and examinations will be provided to compensate for each deficient college level credit.

STA TRAINING AND REQUALIFICATION PROGRAM Page 5 Area I -

General Technical Education (Continued)

A course description for each of the above subjects is provided in the appendices and are designated 'Appendix B through H'.

Training in selected Administrative categories will also be accomplished as indicated in Appendix A.

in addition, an eighty (80) hour period will be provided at the end of Area I

Training for review and semi-final examination.

It is anticipated that Area I will be of thirteen (13) weeks duration, but is dependent on the degree of individual training required.

Area II -

Reactor Operations Training Area I! provides the STA candidate training in the philosophy and details of the design,

function, arrangement and operation of plant systems to assure that the meaning and significance of instrument readings and the effect of control actions are known.

The areas of system training which will be covered are divided into four (4) sections as follows:

Administrative Orders, Regulatory Controls and Plant Procedures Nuclear Steam Supply Systems Balance of Plant Systems Instrument Systems A course description for each of the above areas is provided in the appendices and are designated 'Appendix I through L.

In addition, an eighty (80) hour period will be provided at the end of Area II Training for review and semi-final examination.

Area II will be of fourteen (14) weeks duration.

Area III -

Transient and Accident Response Training The purpose of Area III training is to broaden the STA candidates ability for prompt recognition of and tresponse to unusual events.

The course content will include the following:

Transient Analysis Accident Analysis Nuclear Plant Simulator A course description for each of the above topics is provided in the appendices and are designated 'Appendix M through 0'.

In addition, a two hundred (200) hour period wil be provided at the end of Area III Training for review, semi-final examination, final course written and review board oral examinations and on the job training.

Area III will be of eleven (11) weeks duration.

STA TRAINING AND REQUALIFICATION PROGRAM Page 6 EXAMINATION Periodic tests and quizzes will be administered to evaluate the STA candidates performance and progress during all phases of initial training.

A semi-final examination will also be given at the completion of each general area.

A minimum grade of 70% is considered passing for semi-final examinations.

Upon completion of the initial training program, the STA candidate will be required to satisfactorily pass a course final written examination and review board oral examination.

A grade of 80% or more for both the written and oral portions will be necessary before certification to assume STA duties is granted.

SHIFT TECHNICAL ADVISOR REQUALIFICATION TRAINING PROGRAM Shift Technical Advisor (STA) participation in the requalification program is the primary method employed for the STA to maintain and demonstrate continued proficiency and competence in the area of operational safety.

The items which will be included in the requalification program are as follows:

Assigned individual study Scheduled lectures Simulated problem solving excercises Annual Simulator training Annual written evaluation examination A course description for the items listed above is provided in the appendices and is designated Appendix 'P'.

DOCUMENTATION Documentation attesting to the qualifications and training of Shift Technical Advisors, as set forth in the training and requalification programs, will be retained on site by the Training Section.

These records will be available for review for all participants during their active involvement in this program and for a period of at least two years following their permanent termination of activity in the program.

STA TRAINING AND REQUALIFICATION PROGRAM Page 7 SHIFT TECHNICAL ADVISOR TRAINING AND REQUALIFICATION PROGRAM APPENDICES

STA TRAINING AND REQUALIFICATION PROGRAM Page 8 APPENDIX A General training in the areas designated below is necessary in order to aquaint the student with Station Security and Radiation Health and Safety requirements and how STA duties interface with these considerations.

Training - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> total

1. Duties and Responsibilities of the STA - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
2. Station Physical Security session - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
3. Station Radiation Protection sessions - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
4. Station Emergency Plan introduction session - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
5. Plant tour - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Due to the independent but close association with plant operators, it is essential that the STA possess certain management/supervisory skills in order to maintain the proper working relationship.

Training will, therefore, be provided in the following subjects:

Training - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> total

1. Leadership
2. Interpersonal Communications
3. Motivation of Personnel
4. Problem and Decisional Analysis
5. Command Responsibilities and Limits
6. Stress
7. Human Behavior

STA TRAINING AND REQUALIFICATION PROGRAM Page 9 APPENDIX B ENGINEERING MATHEMATICS Engineering Mathematics consists of material necessary to analyze and characterize concepts covered throughout the Shift Technical Advisor program utilizing mathematical expressions involving calculus.

STA candidates not demonstrating 15 units of college level credit or 240 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

This subject matter will also be practiced during the remainder of the STA program.

1. Variables and functions, algebra review
2. Limits
3. Continuity
4. Derivative
5. Differentiation, of algebraic functions
6. Problems, review
7. Exam
8. Implicit differentiation, derivatives of higher orders
9. Tangents and normals
10. Maximum and minimum
11. Applied problems in maxima and minima
12. Rectiliniar and circular motion, rate of change
13. Problems, review
14. Exam
15. Differentiation of trigonometric functions
16. Differentiation of inverse trigonometric functions
17. Differentiation of exponential and logarithmic functions
18. Differentiation of hyperbolic functions
19. Problems, review
20. Exam
21. Plane vectors
22. Curvilinear motion
23. Differentials
24. Polar coordinates
25. Indeterminent forms
26. Problems, review
27. Exam
28. Fundamental integration formula
29. Integration by parts
30. Trigonometric integrals
31. Trigonometric substitution
32. Integration by partial fractions
33. Integration of hyperbolic functions
34. Application of indefinite integrals

STA TRAINING AND REQUALIFICATION PROGRAM Page 10 APPENDIX B (Continued)

35. Problems, review
36. Exam
37. Definite integral
38. Plane areas by integration
39. Volumes of solids by revolution
40. Moments of inertia
41. Improper integrals
42. Problems, review
43. Exam
44. Infinite sequences and series
45. Tests for convergence and divergence of positive series
46. Computations with series
47. Power series
48. Series expansions of functions
49. Computation using power series
50. Problems, review
51. Exam
52. Partial derivatives
53. Implicit functions
54. Vector differentiation and integration
55. Double integrals
56. Area of a curved surface
57. Triple integrals
58. Differential equations
59. Problems, review
60. Exam

STA TRAINING AND REQUALIFICATION PROGRAM Page 11 APPENDIX C HEAT TRANSFER AND THERMODYNAMICS Heat Transfer and Thermodynamics consists of material necessary to characterize and quantify energy transport conditions existing in the nuclear core and plant systems.

STA candidates not demonstrating 7.5 units of college level credit or 120 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Forty (40) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. First law of thermodynamics, boundary conditions, definition of thermodynamic work, enthalpy.
2. Adiabatic and isothermal processes, heat capacity, entropy
3. Second Law of Thermodynamics.
4. Carnot cycle, saturation and subcooled condition
5. Phase changes, latent heat, boiling, condensing
6. Exam
7. Thermodynamic diagrams P-H, P-S, P-V, T-S
8. Steam and its properties, Mollier diagram, steam tables
9. Energy transport:

conduction, convection, radiation

10. One dimensional heat conduction - equation development
11. One dimensional heat conduction -

semi -

infinite slab, problems

12. Exam
13. Transient heat conduction - equation development
14. Transient heat conduction -

semi -

infinite slab, problems

15. Convective heat transfer
16. Nucleate boiling heat transfer
17. Bulk boiling heat transfer
18. Film boiling heat transfer
19. Exam
20. DNB, DNB as a function of pressure and flow changes
21. Nuclear fuel, one dimensional heat transfer
22. Hot channel factors, LHGR, Fg, Fsh.
23. Equipment: steam generators, heat exchangers
24. Equipment: condenser, heat exchanger
25. Exam
26. Heat balances
27. Plant specifics
28. Plant specifics
29. Review
30. Exam

STA TRAINING AND REQUALIFICATION PROGRAM Page 12 APPENDIX D CHEMISTRY AND RADIOCHEMISTRY Chemistry and Radiochemistry covers material necessary to understand the water chemistry treatment and control techniques utilized in a nuclear plant and concepts necessary to assess health physics hazards of radioactive material.

STA candidates not demonstrating 5 units of college level credit or 80 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Eighty (80) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. Fundamentals:

atomic structure,

valence, periodic
table, molecules
2. Fundamentals:

chemical reactions, chemical equation

3. Chemical reactions: exothermic, endothermic reactions
4. Chemical reactions: equilibrium, reaction rates
5. Chemical reactions:

solubility, extent of reaction, PH

6. Physical chemistry:

gasses Boyles Law, Charles Law

7. Physical chemistry:

liquids critical point, PV diagrams, sur face tension, capillary action

8. Physical chemistry:

fluids - viscosity

9. Review
10. Exam
11. Corrosion:

Galvanic reactions, effect of temperature, stress

12. Corrosion control:

cladding, alloys

13. Primary/secondary water treatment
14. Specific chemistry of interest:

Zr:

H20, Chloride/Stainless, tritium

15. Site-specific specs. (chem)
16. Accident chemistry:

Iodine, transuranics, conductivity, Xenon

17. Radiochemistry:

half life, concentrations of radio-isotopes

18. Health Physics:

effect of radiation on body, allowed limits

19. Review
20. Exam

STA TRAINING AND REQUALIFICATION PROGRAM Page 13 APPENDIX E MATERIAL STRENGTH AND PROPERTIES Material Strength and Properties covers topics necessary to under stand the design characteristics and limitations of metals utilized in nuclear plant construction.

STA candidates not demonstrating 2.5 units of college level credit or 40 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Forty (40) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. Structure of the solid state:

primary bonding (ionic, covalent, metallic), secondary bonding, bonding energy

2. Properties of the solid state:

heat capacity, heat conduc tivity, thermal expansion, elasticity, ductility, toughness, hardness

3. Metallic structure:

crystalline forms, impurities in solids, alloys, imperfections in crystalls, grain boundary

4. Metallic deformation:

elastic deformation (Youngs Modulus),

shear stress, elastic moduli vs. temp.

5. Plastic deformation - critical shear stress, properties of plas tically deformed metals - strain hardening
6. Review exam, recrystallyation (annealing),

hot vs. cold working of metals, creep

7. Fracture:

ductile vs. brittle fracture,

NOT, radiation damage atomic displacement, effects on NOT
8. Site specific parameters:

NOT curve, heatup rate, cooldown rate

9. Review
10. Exam

STA TRAINING AND QUALIFICATION PROGRAM Page 14 APPENDIX F REACTOR PHYSICS & REACTOR CONTROL Reactor Physics consists of material necessary to comprehend nuclear properties and nuclear reactions which determine nuclear reactor characteristics and response.

Reactor Control covers material necessary to understand and describe the dynamic characteristics of Nuclear Reactor Response.

STA candidates not demonstrating 15 units of college level credit or 240 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Eighty (80) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. Neutron economy in reactor core, production of neutrons (U235, PU239), fast fission
2. Neutron economy in' reactor core, losses of neutrons
leakage, absorptions
3. Six factor formula, introduction, fast fission factor
4. Six factor
formula, reproduction
factor, resonance escape probability
5. Six factor formula, thermal utilization, fast and thermal leakage
6. Six factor formula, problems and usage
7. Exam
8. Reactivity, definition, period, start-up rate
9. Prompt and delayed neutrons
10. Inhour equation, derivation, uses
11. Buckling, definition, one group neutron diffusion equation
12. One group neutron diffusion equations, boundary conditions pro blems, reflectors
13. Multigroup neutron theories
14. Heterogeneous system, multiplication factor
15. Control rods, worth, geometry effects, material construction
16. Control rod effect on hot channel factors
17. Control rod worth measurements, differential, integral, drop
18. Exam
19. Moderator temperature coefficient, theory
20. Moderator temperature coefficient use, measurement
21. Xenon poisoning theory, operational difficulties
22. Other fission poisons, Samarium; pressure coefficient
23. Power coefficient (Doppler)
24. Boron Shim operation
25. Burnup effects on coefficients and parameters
26. Reactivity balances, heatup, cooldown, power changes
27. Estimated critical positions and subcritical multiplication
28. Core loading, unloading, sources of neutrons
29. Review
30. Exam

STA TRAINING AND REQUALIFICATION PROGRAM Page 15 APPENDIX G FLUID MECHANICS Fluid Mechanics covers material necessary to characterize and cal culate properties of Fluids and Fluid Systems involved wth a nuclear plant.

STA candidates not demonstrating 7.5 units of college level credit or 120 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Forty (40) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. Properties of fluids, basic definitions, specific weight, spe cific gravity, viscosity
2. Hydrostatic forces on surfaces, equation development
3. Hydrostatic forces on surfaces, problems
4. Exam
5. Fundamentals of fluid flow, definitions, continuity
6. Flow in pipes, Reynolds number
7. flow in pipes, shear stress, viscosity
8. Flow in pipes, loss of head, velocity distribution, friction factor
9. Exam
10. Flow in piping, systems equivalent pipes, branching pipes
11. Flow in one phase water systems:

natural and forced circulation

12. Flow in one phase water systems:

accident and transient cases, noncondensible voiding

13. Two Phase Flow:

pressure drop calculation, slip ratios carryover

14. Measurement of fluid flow:

incompressibles, nozzle, orifices

15. Measurement of fluid flow: compressible theory
16. Measurement of fluid flow:

discharge coefficient, expansion factor, uncertainties

17. Exam
18. Force of moving fluid:

momentum principle, drag, coefficient

19. Force of moving fluid:

lift

20. Force of moving fluid:

water hammer

21. Pumps:

types (centrifugal, positive displacement), pump theory, operating characteristics, curves

22. Pumps:

NPSH, efficiency, cavitation

23. Pumps:

prime movers:

turbine, motors, protection

24. Exam
25. Site specific fluid systems (RCS, CI, etc.)
26. Site specific fluid systems (FW)
27. Site specific fluid system (ECCS, compressed air etc.)
28. Site specific tech. specs.
29. Review
30. Exam

STA TRAINING AND QUALIFICATION PROGRAM Page 16 APPENDIX H ELECTRICAL ENGINEERING Electrical Engineering covers material enabling an understanding of electrical fundmanetal, electrical generation, instrumentation sys tems and protection systems found at a nuclear power station.

STA candidates not demonstrating 7.5 units of college level credit or 120 contact hours in the course requirements listed below will be provided supplemental training in deficient areas.

Eighty (80) hours plant specific and review training will also be provided for all candidiates, regardless of background.

1. Ohms law, series -

parallel circuits

2. Power, energy, Kirchoffs Laws, loop current
3. Node voltages
4. Induction, magnetic fields
5. Capacitance
6. RLC circuits 7, AC circuits
8. 3 Phase systems
9. Review
10. Exam
11. Nuclear Instrumentation:

neutron measurement, source range

12. Nuclear Instrumentation:

intermediate range, power range, self powered

13. Nuclear Instrumentation:

flux mapping, radiation protection

14. Reactor protection System:

design philosophy, (single failure, rehability quality)

15. Reactor Protection Systems:

plant specific setpoint alarms

16. 1 & C:

pressure, level, flow measuring devices

17. I & C:

temperature measuring devices, signal transmission, com puter, VC instrumentation

18. Feedwater control, pressurizer lever control
19. Review
20. Exam
21. Circuit Opening Devices:

fuses, knife blades, horn gaps, ACB, OCB, CB

22. DC systems and conversion equipment:

DC generators diesel power, motor generator sets, synchronous converters, rectifiers

23. Generator/exciter, protection relays, trips pf
24. Transformers:

design, insulation, cooling, loading

25. Voltage Regulators:

UV, OV

26. Electrical system protective relaying
27. Transmission:

system stability, voltage control

28. Motors (AC): characteristics, protection devices
29. Review
30. Exam

STA TRAINING AND REQUALIFICATION PROGRAM Page 17 APPENDIX I ADMINISTRATIVE ORDERS, REGULATORY CONTROLS AND PLANT PROCEDURES Administrative (Station) Orders are declarations of what shall be done with identification of responsibilities for accomplishment.

Regulatory controls refers to the faciity license and title 10 Code of Federal Regulations '

Plant procedures outline the organized system, method, policy, and/or mechanics to accomplish objectives.

Administrative Orders, Regulatory Controls and Plant Procedures Training 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> total Station Orders, regulatory controls and Plant Procedures selected review including the following:

Useage, adherance, review and correction Equipment Outages and Clearance Procedure Plant Design Changes Quality Assurance Program Emergency Procedures Fire Prevention and Fire Brigade Station Logs Shift Relief, Turnover and Manning Responsibilities for Safe Operation and Shutdown Containment Building and Control Room Access Electrical switching and Switchyard and Switchgear Room Access Title 10, Code of Federal Regultions (Appropriate Sections)

Facility License including Technical Specifications and Bases.

Emergency Plan

STA TRAINING AND REQUALIFICATION PROGRAM Page 18 APPENDIX J NUCLEAR STEAM SUPPLY SYSTEMS Knowledge of the nuclear steam supply systems is essential to enable application of engineering analysis to operational situations.

Areas of specific interest are normal operation, off-normal opera tion, systems design limits, alternative uses, failure mode, instru mentation and placement of equipment.

Associated Operating Procedures and Emergency Procedures will be reviewed during each session.

The training will be a mix of approximately 70% classroom instruction and 30% plant/control room study.

Nuclear Steam Supply Training -

160 Hours Total Reactor Coolant System:

Layout, capacity, vessel internals (including purposes, material, assembly and disassembly order)

RCS:

Reactor coolant pump:

operation, capacity curves, power supply failure modes, coastdown.

RCS:

Pressurizer (operation of heaters, capacity to deal with surges, instrumentation)

RCS:

Overpressure protection:

PORV, safety
valves, low temperature overpressure protection (LTOP); heatup and cooldown, Tech. Specs.

Makeup System:

System print, charging pumps (type, capacity),

feed/bleed heat exchanger, suction sources Bleed (Letdown) System:

Capacity, system print, alternatives (RCS Drains etc.), failure modes.

Plant Safeguards:

ECCS capacity, purpose, system layout, logic Plant Safeguards:

ECCS:

water sources, system problems, weak nesses, recirculation mode, NPSH during recirculation.

Heat Removal Systems:

RHR, limits of operation, capacity, starting system.

Vapor Container System:

Theory, system-isolation valves, test ing, definition of integrity, 10 CFR 50 (J).

Vapor Container System:

VC cooling, accident parameters, Tech.

Specs., post accident hydrogen control.

Waste Disposal

Systems, Liquid:

System layout, class 1 and 2 liquids, activity, accident activity, post-accident uses.

STA TRAINING AND REQUALIFICATION PROGRAM Page 19 Appendix J (continued)

Waste Disposal

Systems, gaseous:

System layout, capacity, equipment (tanks, compressors etc.),

activity, releases, accident uses.

Sampling System:

System layout, system operation, accident availability, uses.

Fuel Handling System:

System layout, operation, interlocks.

Ventilation Systems (NSSS)

Component Cooling Water System

STA TRAINING AND QUALIFICATION PROGRAM Page 20 APPENDIX K BALANCE OF PLANT SYSTEMS The Balance of Plant Systems have a decided effect on the NSSS and as such must be studied in detail.

Many of the plant transients and accidents originate in the BOP systems.

Areas of study:

system function, layout, setpoints capacities, failure mode and interrela tion with NSSS.

Associated Operating Procedures and Emergency Procedures will be reviewed during each session.

The training will be a mix of approximately 70%

classroom instruction and 30%

plant/control room study.

Balance of Plant Training - 160 Hours Total Steam System:

System design and layout, capacities secondary side of steam generator,

level, recirc., moisture separation, problems (denting etc.)

Steam System:

Safety valves (capacity, number, setpoints),

MSIV, steam dump atmospheric and condenser),

aux.

steam system, Tech. Specs.

Turbine and Turbine Auxiliaries:

Overview of turbine,

type, stages, extraction, moisture separation, protection.

Feedwater Systems:

Condenser, condensate and boiler feed pumps, chemistry.

Feedwater Systems:

Feedwater heaters (theory, failure),

aux.

feed system (sources of water, alternatives), Tech. Specs.

Circulating Water Systems:

Theory, capacity, failure, Tech.

Spec./EPA limits.

Service Water System:

Layout, purpose: Fire Protection System:

layout, capacity, failure.

Electrical Systems:

Generator and exciter, theory, type protec tion, failure, cooling, fire hazard.

Electrical Distribution:

HV System (outside power, transfor mer), 480V system, tagging system.

Electrical System, Emergency:

Diesel generators logic, opera tion, reliability, battery system.

Ventilation Systems (BOP)

Auxiliary Cooling Systems Service and Instrument Air Systems Assistant Control Operators Inspections and Associated Duties Plant Equipment Operators Inspections and Associated Duties

STA TRAINING AND QUALIFICATION PROGRAM Page 21 APPENDIX L INSTRUMENTATION SYSTEM The NSSS and BOP Instrumentation Systems are the main source of in formation of the STA and shift personnel and as such must be fully known and understood.

Failure modes, sources and magnitudes of indicated errors must be known as well as the instrumentation layout and limits.

Instrumentation System Training - 80 Hours Total Reactor Protection System:

Parameters, setpoints, instruments, logic.

Reactor Protection System:

Reliability, failure modes, errors.

Nuclear Instrumentation:

Layout, reliability failure modes, Tech. Specs., flux mapping system.

Reactor Coolant System Instrumentation:

Parameters, placement of instruments, reliability, failure modes, errors.

Vital Bus:

Layout, power supplies, failure modes and effect; vapor container instrumentation, parameters, reliability, uses.

Rod Control System:

Operation of rods, power supply, failure modes, problems, position indication.

Feedwater Control System:

Logic, instrumentation, failure modes, failure effects.

Steam Geneator Instrumentation:

Level measurement, reliability, failure modes, effect of VC environment, Tech. Specs.

Radiation Detection System:

Detector layout within plant, para meters monitored, failure modes, uses.

Accident uses of Instrumentation-Logic, priority of information, reliability.

STA TRAINING AND RQUALIFICATION PROGRAM Page 22 APPENDIX M TRANSIENT ANALYSIS The transient analysis covers events which can be expected to occur during the lifetime of the plant.

They will not, by definition, cause fuel failure.

The student must understand the transients thoroughly in order to properly interpret and advise.

Without pro per response, transients can escalate into accidents.

Transient Analysis Training - 80 Hours Total Concept and theory of transient and accident analysis; reasons for

analysis, relationship between analysis and Emergency Procedures.

Unit Trip Step and ramp load changes Reactivity Addition Transients:

Continuous rod withdrawal (cold, hot, at power)

Boron dilution.

Reactivity addition transients:

Water accident Feedwater Reactivity addition transients Large load increase Dropped rod Loss of Feedwater Review selected licensee event reports Review Historic Plant Data relative to transients experienced in the past Review automatic action expected under specific transient conditions and manual action required.

Discuss the use of installed plant systems to control or mitigate an accident in which the core is severly damaged.

This training will include the following topics:

A. Incore Instrumentation

1. Use of fixed or movable incore detectors to determine extent of core damage and geometry changes.
2. Use of thermocouples in determining peak temperatures; methods for extended range readings; methods for direct readings at terminal junctions.
3. Methods for printing incore data.

STA TRAINING AND REQUALIFICATION PROGRAM Page 23 Appendix M (continued)

B. Excore Nuclear Instrumentation (NIS)

1. Use of NIS for determination of void formation; void location basis for NIS response as a function of core temperatures and density changes.

C.

Vital Instrumentation

1. Instrumentation response in an accident enviroment; failure sequence (time to failure, method of failure);

indication reliability (actual vs indicated level).

2. Alternative methods for measuring
flows, pressures, levels, and temperatures.
a.

Determination of pressurizer level if all level transmitters fail.

b. Determination of letdown flow with a clogged filter (low flow)
c. Determination of other Reactor Coolant -System parameters if the primary method of measurement has failed.

D. Primary Chemistry

1. Expected chemistry results with severe core damage; consequences of transferring small quantities of liquid outside containment; importance of using leak tight systems.
2. Expected isotopic breakdown for core damage; for clad damage.
3. Corrosion effects of extended immersion in primary water; time to failure.

E. Radiation Monitoring

1. Response of Process and Area Monitors to severe damages; behavior of detectors when saturated; method for detecting radiation readings by direct measurement at detector output (overranged detector); expected accuracy of detectors at different locations; use of detectors to determine extent of core damage.
2. Methods of determining dose rate inside containment from measurements taken outside containment.

F.

Gas Generation

1. Methods of H2 generation during an accident; other sources of gas (Xe, Kr); techniques for venting or disposal of non-condensibles.
2. H2 flammability and explosive limit; sources of 02 in containment or Reactor Coolant System.

STA TRAINING AND R UALIFICATION PROGRAM Page 24 APPENDIX N ACCIDENT ANALYSIS The accident analysis is an evaluation of the worst possible results of various material or mechanical failures. Although the results of the analysis are worse than what would probably occur as a result of such failures the student must know the analysis thoroughly in order to avoid the worst case.

The student must know the basic theory of the analysis, the assumptions made for the start-point and para meter/equipment actions as well as analysis methods and the final result.

Since the analysis often forms the basis for many technical specifications, knowledge in this area will be a valuable assist in areas other than accident response.

Accident Analysis Training - 40 Hours Total Loss of Coolant

-LOCA prevention System responses to LOCA, instrumentation response Assumptions Results Review LOCA Emergency Procedure Loss of Reactor Coolant Flow Scenario, general occurrence Assumptions of analysis Results Review of Emergency Procedure Loss of Load Design aspects, scenario Assumptions Results Review of Emergency Procedures Steam Generator Tube Rupture Scenario, system response Assumptions Results Review of Emergency Procedure Main Steam Line Break Scenario, system response Assumptions Results Review of Emergency Procedures Rod Withdrawl Scenario, system response Assumptions Results Fuel Handling Accident Interlocks Results Health physics aspects

STA TRAINING AND SUALIFICATION PROGRAM Page 25 APPENDIX 0 NUCLEAR PLANT SIMULATOR The Nuclear Plant Simulator constitutes the closest thing to hands on Reactor Operation, including accident conditions.

As

such, participation in this program provides the best method to bring all of the classroom training together.

Nuclear Plant Simulator Training -

120 Hours Total Nuclear plant simulator training as a minimum will include the following:

Reactor and Plant Startup Load Changes at Power Shutdown to Cold Condition Demonstration of Steam Generator Level Manaul Control Load Rejections of Greater than 10%

Failure of Rod Control System Failure of Automatic Steam Generator Level Controls Failure of Pressurizer Level and Pressure Automatic Controls Turbine Trip from Full Power Reactor Trip from Full Power Loss of Normal Feedwater at Full Power Failure Open of Power Operated Relief Valve Stuck Open Pressurizer Safety Valve Loss of Reactor Coolant Pumps at Full Power and Demonstration of Natural Circulation.

Failure Open of One or More Turbine Bypass Valves while at:

a) Full Power b) Hot Standby

STA TRAINING ANDREQUALIFICATION PROGRAM Page 26 APPENDIX 0 (continued)

Loss of all Feedwater (Normal and Emergency)

Loss of Reactor Coolant (small and DBA)

Steam Generator Tube Rupture (small and large)

Loss of RHR Shutdown Cooling with the RCS Temperature 2000 to 300OF Inadvertent Safety Injection while at Power Loss of Offsite Electrical Power Loss of One Train of Onsite Electrical Power

STA TRAINING AND QUALIFICATION PROGRAM Page 27 APPENDIX P REQUALIFICATION PROGRAM ASSIGNED INDIVIDUAL STUDY Shift assignments will be issued on a regualr basis and will include an outline of material to study.

It will be each STA's responsibility to review the assigned subjects and prepare for examination. Self study assignments will include the following:

Procedure Review Station Orders Operating Instructions Emergency Instructions Quality Assurance Procedures Officially processed Procedures Changes Systems Review Selected System piping and instrument diagrams Applicable Electrical one line and emergency diagrams Instrument set point data.

Supplementary Subjects Review Selected Industry Licensee Event Reports Facility Abnormal Occurence Reports Radiation Protection Manual Facility Design Changes Fire Prevention Manual Accident Prevention Manual Facility License Changes Emergency Plan Technical Subjects Review Heat Transfer and Thermodynamics Chemistry and Radiochemistry Material Strength and Properties Reactor Physics Reactor Control Fluid Mechanics Electrical Engineering

STA TRAINING AND REQUALIFICATION PROGRAM Page 28 APPENDIX P (cont'd)

REQUALIFICATION PROGRAM SCHEDULED LECTURES Formal Lectures, emphasizing the STA's role in accident assessment will be conducted periodically.

The sessions, including review and examinations will total no less than forty-eight (48) hours each calendar year.

Films, videotapes and other training aids will be used to supplement the preplanned lectures when appropriate.

However, these aids will not be used as a.substitute for live instruction.

Typical subjects that will be included as part of the lecture series are as follows:

Thermodynamics, Heat Transfer, Fluid Flow Accident Mitigation W/WO Degraded Core Theory and Principles of Operation General and Specific Plant Operating Characteristics Plant Instrumentation and Control Systems Plant Protection System Engineered Safety Systems Normal and Emergency Operating Procedures Radiation Control and Safety Technical Specifications Applicable portions, Code of Federal Regulations Major upcoming events such as refueling

STA TRAINING AND 9 QUALIFICATION PROGRAM Page 29 APPENDIX P (cont'd)

REQUALIFICATION PROGRAM SIMULATED PROBLEM SOLVING EXERCISES Given a

set of expected instrument indications and alarm annunciations under certain accident/abnormal conditions, the STA will be expected to diagnose a hypothetical problem and determine the proper corrective or mitigating measures for the circumstance.

Although the pertinent parameters provided will be factual to the extent design data and operating experience permits, some unrelated or extraneous information will also be included which may be the case under actual operating conditions.

These exercises may be administered in

'Open Book'

form, to be completed on shift, as proctored tests during the lecture sessions or orally in the presence of a member of the Training Staff.

At least four (4) exercises will be administered to each active-STA during a calendar year and will be selected from the following list:

Steam Generator Tube Leak Large LOCA Small LOCA Loss of subcooling, i.e., saturated RCS response Loss of coolant flow and/or natural circulation Loss of instrument air Loss of condenser vacuum Loss of residual heat removal Loss of saltwater cooling Loss of normal feedwater (normal and auxiliary)

Rod drop or stuck rod Inability to move control rods Emergency boration High coolant activity Turbine trip Malfunction of CVCS Reactor trip Main steam line break (inside or outside containment)

NIS failure Rod control malfunction Reactor control and protection system malfunction Loss of Auxiliary Transformer(s) and/or reserve transformer(s)

Loss of all offsite Power Loss of vital or utility bus Loss of DC Bus Emergency Plan Activation

STA TRAINING AND QUALIFICATION PROGRAM Page 30 APPENDIX P (cont'd)

REQUALIFICATION PROGRAM ANNUAL SIMULATOR TRAINING Nuclear Plant simulator exercises related to selected plant transients and emphasizing the role of the STA will be conducted annually; or as scheduling permits, but not to exceed fifteen months from the last such training.

To the extent possible, it is the intent that the STA participate in exercises along with a shift operating crew utilizing the

'Team Training' concept.

The training session will be of forty (40) hours duration.

STA TRAINING AND UALIFICATION PROGRAM Page 31 APPENDIX P (cont'd)

REQUALIFICATION PROGRAM ANNUAL WRITTEN REQUALIFICATION EXAMINATION A comprehensive written STA examination will be administered annually.

The examination shall be similar to NRC operator examinations in length and format, however, the content will reflect STA duties and training and emphasize testing of the STA's analytical skills.

An overall grade of 80% with no one section less than 70% on the annual examination is considered acceptable.

Any STA failing to meet this criterion shall be assigned to accelerated training in the deficient area(s) until re-testing successfully.

The above examination will be graded and filed by the site training section and will be retained as specified under documentation.

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