ML18139B883
| ML18139B883 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/24/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM 277, NUDOCS 8206010583 | |
| Download: ML18139B883 (27) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND., VIRGINIA 23261 R.H.LEASBUHG V.roE PRESIDENT NucLEA.ll OPBRA"t.IONS May 24, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
SURRY POWER STATION Serial No. 277 NO/DWL,FBC:acm Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RE: NUREG-0737 ITEMS I.A.2.1 AND II.B.4 In response to your request for additional information dated April 29, 1982, regarding the Upgraded SRO and RO Training Program (Item I.A.2.1) and Training for Mitigating Core Damage (Item II.B.4), the following information is provided: - Specific responses to questions regarding the Surry Power Station Training and Requalification Programs. * (References made to remaining enclosures.) - Surry Power Station Organizational Chart. - RO/SRO Training Course Outline. -
STA Training Course Outline. - RO/SRO Training Course Schedule.
We trust that this information will provide the necessary detail for the NRC Staff/consultants to complete their review of the subject NUREG-0737 items.
Please contact us if we can be of further assistance.
cc:
Dr. R. T. Liner Science Applications, Inc.
1710 Goodridge Drive McLean, Virginia 22102 R.H. Leasburg
e e
REPLY TO LICENSING ACTION REQUEST FOR ADDITIONAL INFORMATION A. T~aining Program
- 1.
Lectures and quizzes are provided for all RO/SRO Licensed Managment and Operations Personnel and Shift Technical Advisors.
See Enclosure 2 for the Organization Chart of those personnel who receive training in Accident Mitigation.
~ 2.
The RO/SRO Training P_rogram involves at least 80 contact hours of Heat Transfer, Fluid Flow, Thermodynamics, and Accident Mitigation.
The RO/SRO Retraining Program, which follows the Training Program Outline but has less scheduled time, encompasses at least 50' contact hours of Heat Transfer, Fluid Flow, Thermodynamics and Accident Mitigation.
Shift Technical Advisors receive 40 contact hours of Heat Transfer, Fluid Flow and Thermodynamics.
They also receive 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Accident Analysis and more than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of Systems and Emergency/Abnormal Procedures in classroom and simulator training sessions.
After this initial training they are enrolled in the RO/SRO Retraining Program.
See Enclosure 3 & 4 for program outlines.
See Enclosure_5 for length of instruction (contact hours).
- 3.
Increased emphasis has been placed on reactor and plant transients of both normal and abnormal nature.
The use of the simulator has, in itself, provided the necessary increased emphasis but the contact
, hours have also been increased in this area.
- 4.
The RO/SRO Training Program includes Heat Transfer, Fluid Flow and Thermodynamics and the basic physics necessary to prerequisite those courses.
Calculations are performed to show magnitude and reinforce the concepts taught.
The simulator is also used to reinforce and help students to apply the concepts taught.
These teaching techniques have been incorporated as our attempt to satisfy Mr.
Denton's concern for the knowledge level of nuclear operators.
See for a course outline.
- 5.
The RO/SRO Training Program includes a lesson on LOCA Mitigation which was specifically designed based on Enclosure 3 of Mr. Denton's letter and is Item #45 of Enclosure 3.
e B.
Requalification Program
- 1.
The Requalification Program uses the same lesson plans as the initial Training Program thus the course outline is the same.
The Requali-fication Program only differs in that it has less contact hours of instruction for two reasons:
- a.
.The material is covered to recoup and reinforce previous knowledge.
- b.
Shift work allows the licensed operator to be trained four days every five weeks.
The material is presented in the same fashion as Item A-4, thus is in keeping with the level of detail required by Mr. Denton.
- 2.
As above, the Requalification Program is essentially the same as the initial Training Program and satisfies Enclosure 3 of Mr. Denton's letter since Enclosure 3 was the basis for LOCA Mitigation.
See Item #45 of Enclosure 3.
- 3.
Instructors are kept apprised of current operating history, problems and changes to procedures and administrative limitations by required procedure reviews and required reading which encompass the areas above plus many other subjects. All licensed instructors are enrolled in the Vepco LORP.
- 4.
Our list of reactor control manipulations, stipulated in the Requalification Program, need.not be changed since:
I a.
- b.
- c.
Our Annual Item 3 is the same as Mr. Denton's Item 5 with the exception of "or recirculation flow" which is not applicable to our plant.
Our Bi-Annual Item 3 is the same as Mr. Denton's Item 8.
Our Bi-Annual Item 4 is the same as Mr. Denton's Item 9.
- 5.
The Requalification Program is the same as the initial Training Program thus the lecture series is presented as indicated by Item B-1.
Quizzes are given for each retraining session.
The Organization Chart is the same and is Enclosure 2.
- 6.
The RO/SRO Retraining Program encompasses at least 50 contact hours of Heat Transfer, Fluid Flow, Thermodynamics and Accident Mitigation.
Less time is appropriated by the two reasons given in Item 1.
e
-...... l. --.. **-**------*-* **1 OPERATIONS SUPERINTENDENT I*
(SRO)
I STATION ORGANIZATION FOR TRAINING iDENTIFICATION STATION MANAGER ASSISTANT
.J*
i I OPERATIONS COORDINATORS (SRO)
SENIOR NUCLEAR TRAINING COORDINATOR SRO SHIFT SUPERVISOR (SRO)
ASSISTANT l
- i I SUPT. TECH.
SERVICES SHIFT SUPERVISOR
______ (.._S....,R __ Oe..) --------
1 I
- I
... ' ---S-H-IF_T_T_E_C_H_. __ _,
ADVISORS I
CONTROL ROOM OPERATOR (RO)
-~1_*
- ' CONTROL - ROOM OPERATOR I**
I TRAINEE
- Receives initial training (11 months) in preparation for licensing *
- Previously received initial training and currently enrolled in the Retraining Program.
e
- 2.
- 8. Properties of Solids
- 9.
- 10.
a.. *Structure of Matter
- b. Density
- c. Elasticity
- d.
Stress and Strain
- e. Brittle and Ductile Material
- f.
Yield and Ultimate Strength l.* Nil-Ductility Temperature Properties of Fluids
- a. Density
- b. Pressure
- c.
Archimedes Principle Temperature and Expansion
- a.
Tempe~ature and Thermal Energy
- b.
Temperature Scales
- c. Linear, Area, and Volume Expansion d; Expansion of Water
- 11.
Quantity ~f Heat
- a. Definition of Heat b..
Heat and Mechanical Energy
- c.
Specific Heat Capacity
- d.
Change of Phase
- 12.
Thermal Pioperties of Matter
- a.
Ideal Gas.
- b.
Ideal Gas Law
- 13.
Thermodynamics
- a.
Heat and Work
, b. Firsf Law of Thermodynamics
- c.
Second Law of Thermodynamics
- d.
Properties of Water and Steam
- e.
Steam Tables - Hollier Diagram
- f.
Thermodynamic Cycles
- 14.
Fluid Dynamics
- a.
Fluid Flow
- b.
Continuity Equation
- c.
Bernoulli's Equation
- d.
Reynolds Nwnber
- e.
Fluid Friction
- f.
Pump Characteristics e
I
- 15.
Heat Transfer
- b.
- c.
c~nduction Radiation Convection e
- d.
Boiling Heat Transfer
- 16. Health Physics I
- a.
General Employee Training
- b.
Definitions and Units 3
- c. Radiation Control Procedures
- d.
Respiratory Protection
- 17.
Chemistry
- a.
Introduction to Chemistry
- b.
Chemical Terms
- c.
Fundamentals of Chemistry
- d.
Chemical Reactions in Nuclear Power Plants
- e.
Nuclear Power Plant Chemistry Control
- f.
Water Analysis fqr Nuclear Power Plants
- 18.
Nuclear Physics
- a.
Atomic Structure
- b.
Nuclear Terminology
- c.
Properties of the Nucleus
- d.
Binding Energy.and Mass Defect
- e.
Nuclear Fission
- 1) Fission Cross Sections
- 2)
Mechanism of the Fission Process
- 3) Reac~ion Rate and Power Production
- 4) Fission Products
- 5) Radioactivity of Fission Products
- 19.
Neutron Physics
- a.
Neutron Sources
- b.
Neutron Reactions
- c.
Cross Sections
- 1)
Macroscopic Cross Section and Hean Free Patch
- 2)
Cross Section Energy Dependence
- d.
Classification of Neutrons
- e.
Neutron Flux and Reaction Rate
- f.
Neutron Moderation e
SRO/RO 81-3 LICENSE CLASS OUTLINE
- 1.
Orientation
- a.
Introduction to Course
- b.
Taking Notes
- c.
Study ~abits
- d.
Taking Exams
- 2.
Mathematics
- a. Fractions*
- b.
Decimal Fractions
- c.
Percentage
- d.
Square Roots of Numbers
- 3.
Algebra
- a.
Operations with Algebraic Expressions
- b.
Algebraic Equations c~
Special Products and Factoring
- d.
Graphing
- e.
Exponents, Powers, and Roots
- f.
Scientific Notation
- g. Ratio, Proportion, Variation
- 4.
Geometry
- a. Essentials of Plane Geometry
- b. *solid Figures
- 5.
Trigonometry
- a.
Trigonometric Functions
- b.
Sol~tions of Triangles
- c.
Vectors
- 6.
Logarithms
- a.
Introduction
- b.
Laws of Logarithms
- c.
Base Ten and Natural Logarithms
- 7.
Mechanics
- a.
Systems of Units and Measurement
- b.
Uniformly Accelerated Motion
- c.
Relationship Between Mass and Weight
- d.
Energy, Work, Power
- e.
Impulse and Momentum
- f.
Simple Machines
- g.
Friction
- 20.
4
- 1) Logarithmic Energy Decrement
- 2)
Slowing Down Power
- 3) Moderating Ratio
- 4) Fermi Age and Thermal Diffusion Length
- g.
Neutron Multiplication Reactor Kinetics
-a. Reactivity and Period
- b. Fission Neutrons
- 1)
Prompt and Delayed
- 2)
Generation Time,. Lifetime and Travel
- 3) P and P eff
- c.
Exponential Power Equation
- 21.
Reactivity Coefficients and Poison Effects
- a. Fuel Temperature Coefficient
- b.
Moderator Temperature Coefficient
- c.
Void Coefficient
- d.
Pressure Coefficient
- e. Redistribution Coefficient
- f. Xenon
- g.
- 22.
Subcritical Multiplication and Installed Sources
- 23.
Reactivity Control
- 24.
Flux Distribution and Control
- a. Distribution and Control
- b.
~$ and Axial Offset
- c.
Hot Channel Factors
- 25.
ECP, OP-lF and 1/M Plots
- a.
- b.
OP-lF, Shutdown Margin
- c.
1/M Plots
- 26.
Reactor Vessel & Core Components
- 27.
Containment Vessel & Subsystems
- 28.
f 5
- 29.
Residual Heat Removal System 3Q.
Chemical and Volume Control System
- 31.
Secondary Systems I
- a.
- f.
Reheat Steam
~b.
- g.
- c.
Main Feed
- h.
- d.
Main Condensate.
- i. Auxiliary Feed System
- e. Main Turbine
- 32. Health Physics II
- a.
Radiation Detection
- b.
Radiation Detection Devices
- c.
Detector Efficiency Determination
- d.
Radiation Monitoring System
- e.
Technical Specifications
- f.
- g.
- 33.
Nuclear Instrumentation
- a. Excore Instriµnentation
- b.
Incore. Flux Mapping ~ystem
- c.
Incore Thermocouple System
- 34.
Tave/Rod Control a.* ll.T/Tave Control
- b.
Tave Control System
- c.
Rod Control System
- d.
Rod Posit.ion Indication System
- 35.
Reactor Protection and Control
- a.
Reactor Protection - General
- b.
Process Protection Instrumentation
- c.
Overpower-Overtemperature Delta T Protection
- d.
Miscellaneous RCS Instrumentation
- e. Pressurizer Pressure Control System
- f.
Pressurizer Level Control System
- g.
Steam Dump Control System
- h.
Steam Generator Level Control System
- 36.
Main Turbine Protection and Control
e 6
- 37.
Engineered Safeguards Systems
- 1
- ~~fety Injection System
- b.
Containment Spray System
- c.
Recirc*Spray System
- d.
CLS
- 38.
Secondary Systems II
-a.
Turbine Lube Oil
- b.
- c.
Gland Seal
- d.
Auxiliary Steam
- e.
Circulating wa*ter
- f.
Bearing Cooling Water
- g.
Hydrogen Gas
- h.
Hydrogen Seal Oil
- i.
Chemical Feed
- j. Secondary Drains_
- k.
Condensate Polishing
- 1.
S/G Recirc. and N2 Systems
- 39.
Support Systems
- a.
Service and Instrument Air
- b.
Fire and Domestic Water
- c.
Fuel Oil
- d.
- e.
Component Cooling
- f.
Chilled Water
- g.
Charging Pump Cooling Water
- h.
Primary Grade Water
- i.
Boron Recovery
- j. Liquid Waste
- k.
Gaseous Waste
- 1. Flash Evaporator
- m.
Ventilation
- n.
Sampling
- o.
Vents and Drains
- p.
Overpressure Hitigating System
- q.
Core Cooling Monitor
- r.
PORV and Safety Monitoring
- s. Auxiliary Shutdown Panel
- t. Status Lights
- 40. Electrical Theory
- a. Electrical Terms
- b.
Battery Theory
- c.
Magnetism
e
- d.
Electrical Generation, AC and DC
- e. Electrical Instrumentation f.. Electrical Hazards
- g.
Synchronization
- 41.
Electrical Systems
- a.
Main Generator and Switchyard
- 1) Exciter
- 2) Breakers
==
3). Operation
-4)
- b.
Normal Distribution
- 1) 4160 V
- 2) *480 V
- 3)
- 4)
Screenwell Distribution Lighting
- c.
Emergency Distribution
- 1) 4160 V
- 2) 480 V
- 3) Vital Bus
- 4)
DC Bus 4Z.
Administrative Procedures
- 43.
Operating Procedures
- 44.
Annunciator Procedures
- 45.
- 46.
Accident Analysis
- 47.
Emergency Procedures
- 48.
Abnormal Procedures
- 49.
Transient Analysis
- 50.
Fuel Handling
- 51.
Emergency Plan and EPIP's
- 52.
SRO Management Course e
e STA TRAINING COURSE OUTLINE College Level Fundamental Education Mathematics.
A.
Algebra
- 1. Basis Concepts
- 2.
Algebraic operations
- 3.
Linear equations
- 4.
Exponents and radicals s.. Roots B.
Logarithms
- 1. Definition
- 2.
Rules of logarithms
- 3.
Base 10 and natural logarithms
- 4.
Exponential and logarithmic equations C.
Geometry and Trigonometry
- 1.
Plane geometry
- 2.
Solid geometry
- 3.
Trigonometric functions
- 4.
Vectors and vector e>perations t,Enclosure 4 Contact Hours 40
Contact Hours D.
Specialized Mathematics
- 1. Ratios and proportions
- 2.
Graphing techniques
.3.
Systems of equations E.- Differential Calculus
- 1. Limits and continuity
- 2. Derivatives
- 3. Applications of derivatives F.
Integral Calculus
/1. Antiderivatives
- 2. Definite integrals
- 3. Applications of integrals G.
Differential Equations
- 1. *First *order
- 2. Applications of first order
- 3.
Linear equations
- 4.
Applic~tions of linear equations R.
Partial Differential Equations Reactor Theory.
A.
Basic Nuclear Physics
- 1.
Atomic structure
- 2.
Nuclear terminology
- 3.
Properties and structure of the nucleus
- 4.
Mass defect and binding en~rgy B.
Nuclear Fissfon
- 1.
Microscopic and macroscopic cross sections
- 2.
Fission process
- 3. Reaction rates and power production
- 4.
Fission products C.
Neutron Kinetics
- l. Neutron sources
- 2.
Reactions and cross sections
- 3.
Neutron flux
- 4.
Neutron moderation 5.. Neutron muliplication (including subcritical)
- 6.
Diffusion theory
- i. Criticality theory 48
e
- D.
Reactivitv Coefficients and Poisons
- 1. Fuel temperature coefficient
- 2.
Hoderator temperature coefficient
- 3.
Void coefficient
- 4. Pressure coefficient
- 5. Reaistribution coefficient 6 *. Xenon 7~
- 8.
- 9.
Other poisons (control rods, structural materials, etc.)
Reactor Chemistry.
-A.
Purpose B.
Terminology C.
Sources of Makeup Water
- 1. Flash Evaporator
- 2. Polishing Demineralizer
- 3.
Condensate Storage Tanks D.
Secondary Chemistry *
- 1. Type of chemistry control
- 2.
Condenser leakage effects
- 3.
Steam Generator chemistry problems
- 4.
Steam Generator corrosion 5~
Secondary chemistry specifications E.
Primarv Chemistry
- 1.
Chemical addition
- 2.
Demineralization
- 3.
P~imary chemistry specifications
- 4.
Nulcear reactions S.
Corrosion Nuclear Materials..
A.
Introduction
- 1.
Charact.erist.ics of an "Ideal metal"
- 2.
Failure modes of m~~als
- 3.
Metalic structure
- 4.
Radiation effects on metals e
Contact Hours 16 16.
- e.
B.
Fuel Element Design C.
Reactor Vessel Design D.
Steam Generator Design
- E.
ASHE* Section III Design Criteria Thermal Sciences.
A.
Thermodynamics
- l. Laws of Thermodynamics
- 2. Properities of steam and water
- B.
Fluid Dvnamics
- 1. Fluid statics
- 2. Bernoulli's Equation,
- 3. Static and dynamic pressures
- 4. Laminar and turbulent flow
- 5. ***Two phase flow C.
Heat Transfer e
Contact Hours 40
- 1. Fundamentals (conduction, convection, radiation)
- 2.
Pool boiling
- 3. Forced convection boiling
- 4.
Departure from Nucleate Boiling (DNB)
- 5. Heat exchangers D.
Reactor Thermal Cycle Nuclear Radiation Protection and Health Physics.
16 A.
Radiation
- 1.
Sources of radiation
- 2.
Types or radiation
- 3. Effects of radiation on matter B.
Biological Effects
- 1.
Micro (atomic) effects
- 2.
Macro ( cell)* effects
- 3.
Acute radiation effects
- 4.
Chronic radiation e'f.f ect:s
e C.
Radiation Protection
- 1.
Time, distance, and shielding
- 2. Anti-contamination clothing
- 3. Respiratory protection TOTAI.
Applied :Fundamentals - Plant Specific Reactor Technology.
A.
flux Distribution and Control
- 1. Axial flux distribution
- 2.
Radial flux distribution
- 3.
~~ and axial offset
- 4. Bot channel factors
- 5. Control rods
- 6.
Boron B.
Reactor Core
- 1.
Core materials
- 2. The%mal peformance
- 3.
Core description
- 4.
Core capability C.
Core Physics Data
- 1. Startup physics data
- 2.
Core flux mapping
- 3.
Core thermocouple mapping D.
Reactivity Procedure l,
Estimated Critical Position (ECP) 2, Shutdown Margin Calculation (OP-lF)
Instrumentation and Control.
A.
Basic Instrumentation
- 1.
Flow measuring dev{ces
- 2.
Pressure measuring devices Contact Hours lli 32
- 32 ----
e 3:
Temperature measuring devices
- 4.
Level/volume measuring devices S.
Miscellaneous measuring devices B.
Control Theory
- 1.
Flow control circuits
- 2.
Pressure control circuits
- 3.
Temperature control circuits
- 4.
Level/volume control circuits S.
Miscellaneous control circuits e*
Contact Hours TOTAL 64 Management/Skills Communications.
Problem Solving.
Dec*ision Analysis.
TOTAI.
Plant Systems Primary Systems.
A.
Reactor Coolant Svstem B.
Residual Heat Removal s~~tem C.
Chemical and Volume Control Svstem
~-
Nuclear Instrumeotatioc Svstem E.
- 1.
Excore
- 2.
Incore T * /Rod Control ave
- 1.
- 2.
- 3.
- 4.
AT/!
T ave ave Control Rod Control Rod Position Indic~~~on 8
8 8
24
e F. Reactor Protection and Control
- 1. Reactor Protection* General
- 2.
Process Protection Instrumentation
- 3.
Overpower/Overtemperature ~T Protection
- 4.
Pressurizer Pressure Control and Protection
- 5.
Pressurizer Level Control and Protection
- 6.
Steam Dump Control
- 7.
Steam Generator Level Control and Protection Secondary Systems.
A.
- .Main Steam System B.
Main Feedwater Svstem D.
Main Condensate System E.
Main Turbine F.
Turbine Control and Protection G.
Steam Generator Blowdown System R.
Steam Dumps I. Circulating Water System J.
Service Water System Support System.
A.
Component Cooling Water Svstem B.
Chilled Component Cooling Water Syst~m C.
Charging Pumi:> Cooling Water System D.
Primary Grade Water System E.
Liguid Waste System F.
Gaseous Waste Svstem G.
Ventilation Svstem H.
Core Cooling ~onitor e
Contact Hours
e I.
PORV and Safety Valve System J. Auxiliary Shutdown Panel K. - St:?tus Lights L.
Loose Parts Monitoring System (North *Anna only)
M.
Radiation Monitoring
- 1. General Detector Curve
- 2. Radiation Monitoring System Safeguard Systems.
A.
Safety Injection System B.
Containment C.
Containment Vacuum Svstem D.
Containment Spray System E. Recirculation s~rav Svstem F.
Consequence limiting Safeguards G.
Auxiliary Feedwater Svstem Electrical Svstems.
A.
Normal Distribution
- 1.
4160 vac
- 2.
480 vac
- 3. Screenwell distribution
- 4. Lighting B.
Emergency Dist.ribution
- 1.
4160 vac
- 2.
480 vac
- 3. Vital Busses
- 4. nc* distribution TOTAL e
Contact* Hours 240
e Administrative Controls Responsibilities for Safe Operation and Shutdown.
Equipment Outages and Clearance Procedures.
Use of Procedures.
Plant Modifications.
Shift Relief Turnover and Manning.
Containment Access *.
Maintaining Cognizance of Plant Status..
Administrative Requirements of the STA.
Radiological Emergency Plan.
Title 10 Code of Federal Regulations.
Plant Technical Specifications (including bases).
TOT.AI.
Transient/Accident Analysis and Emergency Procetl~=~s Accident/Transient Analvsis.
A.
Transient Analysis Methodology
.B.
Core Reload Design C.
Phvsics Related Safetv Analvsis In~ut D *. Core Thermal Hydraulic Analysis E.
System Transient Analysis F.
Non-LOCA Transient Analvsis
- 1.
Rod withdrawal from subcritical
- 2.
Rod withdrawal at power
- 3.
Dropped rod
- 4.
Feedwater System malfunction
- 5.
Excessive load increase
- 6.
eves-malfunction
- 7.
Startup of inactive reactor coolant :oop
- Contact Hours 40
---~~
e Co'ntact Hours 8~
Loss of flow
- 9.
Single rod withdrawl 11"1..
Loss of normal feedwater
- 12.
Feedline break
- 13. -Steam Generator tube rupture
- 14.
Inadvertant Safety Injec~ion
- 15. Steamline break
'-J.6.
Rod ejection 17
- Locked rotor (fuel performance)
G.. Loss.of Coolant Accident
- 1.
Large
- 2.
Small ll. Best Estimate Transient Analysis
- 1. North Anna cooldown *event
- 2. Surry pump coastdown
- 3. Simulator loss of load comparison TOTAL 40 -
Simulator Training The plant evolutions, transients and events listed below should be conducted along with any others deemed necessary.
The primary objective should be to d~onstrate plant and operator response to a given condition or event and not to 4evelop the contr.ol manipulation expertise of.the trainee..
The trainee/ins.tructor ratio should not exceed 4: 1 except when the Training" concept is being utilized.
"Team I
Simulator exercises should be preceded by a period of discussion of the planned exerc~ses addressing expected response of ;he plant and applicable*
plant*procedures to be used.
Approximately 80 contact hours are required with about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in*the classroom and 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> on the simulator.
I I
e e
Fo~lowing each exercise 4emo~strating a transient of emergency event, an
........................... ~~.i.que discussion should be held to enhance the* trainees' under-standing of that particular exercise.
When the simulator is not plant-specific, the. training should be tailored to the speci£ic plant as much as*
PWR Simulator Exercises Contact Hours Malfunctions.
A.
Single
- 1.
Steam Generator tube rupture
- 2. Loss of rod control
- 3.
Loss of feedwater
- 4. Reactor/turbine/generator trip
- 5.
Small break LOCA
- 6.
Large break LOCA
- 7. Loss of RCS pressure
- 8.
Steam Generator level malfunction
- 9. Uncontrolled cooldown of RCS
- 10.
Loss. of flow
- 11. Loss of electrical bus (4160 vac)
- 12.
Loss of RHR B.. Multiple Malfunctions to be determined based on the class's performance Normal Ot>erations.
A.
Reactor startuu B.
Reactor shutdown C.
Power maneuvers TQTAL 80
OCT* 12 OCT 13 NOV 10 NOV 11 NOV 12 NOV 13 NOV 16 NOV 17 NOV 18 NOV 19 NOV 20 NOV 23 NOV 24 NOV 25 NOV 26 NOV 27 NOV 30 DEC 1
DEC 2
DEC 3
DEC 4
DEC 7
DEC 8
DEC 9
DEC 10 DEC 11 DEC 14 DEC 15 DEC 16 DEC 17 DEC 18 DEC 21 DEC 22 DEC 23 DEC 24 DEC 25 DEC 28 DEC 29 DEC 30 DEC 31 JAN 1
e e
RO CLASS 81-3 SCHEDULE Orientation FOUR WEEKS IN PLANT
- Holiday Math Math Algebra Algebra Algebra Geometry Trigonometry Trigonometry Logarithms Logarithms Holiday Holiday Review Exam I Mechanics Mechanics Properties of Solids
'Properties of Solids Properties of Liquids Temperature and Expansion Thermal Properties of Matter Thermodynamics Thermodynamics Thermodynamics Fluid Flow Fluid Flow Heat Transfer Heat Transfer Review Exam II Holiday Holiday Health Physics I Health Physics I Chemistry Chemistry Holiday
JAN 4
JAN 5
JAN* 6 JAN 7
JAN 8
JAN 11 JAN 12 JAN 13 JAN 14
- JAN 15 JAN 18 JAN 19 JAN 20 JAN 21 JAN 22 JAN 25 JAN 26 JAN 27 JAN 28 JAN 29 FEB l
1' MARCH 14 MARCH 15 MARCH 16 MARCH 17 MARCH 18 MARCH 19 MARCH 22 MARCH 23 MARCH 24 MARCH 25 MARCH 26 MARCH 29 MARCH 30 MARCH 31 APRIL 1
APRIL 2
APRIL 5
APRIL 6
APRIL 7
APRIL 8
APRIL 9
e Nuclear Physics Nuclear Physics Nuclear Physics Neutron Physics Neutron Physics Reactor Kinetics Reactor Kinetics Reactor Kinetics Reactivity Coefficients & Poison Effects Reactivity Coefficients & Poison Effects Subcritical Multiplication & Installed Sources Reactivity Control Flux Distribution & Control Core Thermal Performance Delta Flux and Axial Offset ECP & 1/M PLOT I s ECP & 1/M PLOT's Shutdown Margin Calculation Review Exam III SIX WEEKS IN PLANT Reactor Vessel & Core Components Containment & Cont. Systems Reactor Coolant System Reactor Coolant System Tech. 'Spec. Section lJ 2J 3.1 / Simulator Residual Heat Removal System Chemical & Volume Control System Chemical & Volume Control System Main Steam & Steam Generators Main Feed & Condensate_Systems / Simulator Main Turbine; Reheat & Extraction Steam Systems High Pressure & Low Press. Heater Dr. Systems Aux. Feed System Review Exam IV Health Physics II/ Simulator Health Physics II Nuclear Instrumentation Nuclear Instrumentation Holiday
A:':::'.:!. 12 APRIL 13 APRIL 14 APRIL 15 APRIL 16 APRIL 19 APRIL 20 APRIL 21
.APRIL 22
_.APRIL 23 APRIL 26 APRIL 27-APRIL 28 APRIL 29 APRIL 30 MAY 3
MAY 4
MAY 5
MAY 6
MAY 7
MAY 10 MAY 11 MAY 12 MAY 13 MAY 14 MAY 17 MAY 18 MAY 19 MAY 20 MAY 21 MAY 24 MAY 25 MAY 26 MAY 27 MAY 28 MAY 31 JUNE 1
JUNE 2
JUNE 3
.JUNE 4
JUNE
.JUNE 7
8 JUNE 9
JUNE 10 JUNE 11 e
Nuclear Instrumentation Tave/Rod Control Tave/Rod Control e
Reactor Protection & Control Reactor Protection & Control Reactor Protection & Control Main Turbine Protection & Control Simulator Simulator Simulator Simulator Engineering Safeguards Systems
. Engineering Safeguards.Systems Review Exam V Simulator
- Secondary Systems II Secondary Systems II Secondary Systems II Secondary Systems II/ Simulator Simulator Support Systems Support Sy,stems Support Systems Support Systems/ Simulator Simulator Electrical Theory Electrical Systems Electrical Systems Electrical Systems/ Simulator Simulator Oral Exams Review Exam VI Simulator Holiday Transient Analysis Transient Analysis Transient Analysis Transient Analysis
- Transient Analysis Administrative Procedures Emergency Procedures Abnormal Procedure*s Abnormal Procedures/ Simulator
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JUNE 14
.JUNE JS
.JUNE.16
.JUNE 17 JUNE 18 JUNE 21 JUNE 22 JnNE 23 JUNE 24 JUNE 25 JUNE 28 JUNE 29 JUNE 30 JULY l
JULY 2
JULY 5
JULY 6
JULY 7
JULY *8 JULY 9
JULY 12 JULY 13
.JULY *14 JULY 15 JULY 16 JULY 19 JULY 20 JULY 21 JULY 22 JULY 23 JULY 26 JULY 27 JULY 28 JULY 29 JULY 30 AUG 2
AUG 3
AUG 4
AUG 5
AUG 6
AUG 9
AUG 10 AUG 11 AUG 12 AUG -13 Simulator Operating Procedures Annunciator Procedures Review Exam VII Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Start-up Cert.
Holiday Management Program Management Program Management Program Management Program In Plant In Plant In Plant In Plant In Plant In Plant In Plant In Plant In Plant In Plant Simulator Fuel Handling Emergency Plan LOCA & LOCA Mitigation Review/ Simulator Exam VIII e
LER's & Recent Experiences LER's & R~cent Experiences Instrument Failure Analysis Instrum~nt Failure Analysis/ Simulator Simulator Oral Exams Simulator / Plant Walk Thru's Simulator / Plant Walk Thru's Simulator / Plant Walk Thru's Simulator Walk Thru's
AUG 16 AUG i:7 AUG 18 AUG 19 AUG 20 AUG 23 AUG 24 AUG 25 AUG 26
- AUG 27 AUG 30 AUG 31
- SEPT 1 SEPT 2 SEPT 3 e
e Audit Exam Week (Exam IX)
Audit Exam Week (Exam IX)
Audit Exam Week (Exam IX)
Audit Exam Week (Exam IX)
Audit Exam Week (Exam IX)
Review Heat Transfer & Fluid Flow/ Simulator Review Reactor Theory Review Chemistry & Health Physics Review Instrumentation & Control Simulator NRC EXAM WEEK NRC EXAM WEEK NRC EXAM WEEK NRC EXAM WEEK NRC EXAM WEEK