ML18347A506
| ML18347A506 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/06/1975 |
| From: | Sewell R Consumers Power Co |
| To: | Collins P Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A506 (13) | |
Text
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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 Mr. Paul F. Collins Chief Operator Licensing Branch Division of Reactor Licensing US Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Collins:
March 6, 1975 Re: Docket 50-255 License DPR-20 Palisades Plant Attached is a copy of a program titled "Palisades Plant Train-ing Program, Hot License Candidates." This program is submitted for your review and approval.
Yours very truly, RBS/ww Ralph B. Sewell Nuclear Licensing Administrator CC : JGKeppler, USNRC
PALISADES PLANT Training Program Hot License Candidates This program is proposed for use at the Palisades Plant when the option of using a simulator for the demonstration portion of.the reactor operator's license exam is.desired as described in P. F. Collins letter to L. M. Hausler dated October 3, 1974.
The objective of this program is to prepare license candidates, as thoroughly as practical, in fundamentals of plant operation, and re-sponse to abnormal or emergency conditions. It is our philosophy that the better a person understands the basic theory, the better his judg-ment will be in abnormal situations.
We, therefore, concentrate heavily on this area plus the background (math, general science, basic nuclear physics, etc) for this material.
Prerequisites - Prior to entering the program, each candidate shall have a minimum of.one-year experience as an auxiliary operator at the Palisades Plant.
The candidate shall have satisfactorily completed the "Nuclear Power Plant Steam and Mechanical Fundamentals" course.
He shall have satisfactorily completed the RWP exemption tests.
A review of basic mathematics shall also be satisfactorily completed.
Staff members, other than auxiliary operators, wishing to become licensed will be considered on an individual basis as to their eligibility and prerequisites.
These candidates will be subjected to a comparable program tailored to their specific needs..
Training Program ~ The formal full-time training program will be, in general, in accordance with the schedule set forth in Attachment A.
This attachment tabulates the classropm topics to be covered.
Weekly quizzes are administered and, quite ofi;en, daily.quizzes are administered in these classroom sessions.
An instructor is in attendance during all classroom activities and evaluates progress of individual trainees.
Plant systems and equipment training include work in the control room and the plant to follow through procedures and locate all equipment
and controls.
Checklists are used to point out* individual activities to be accomplished for a number of the more important systems.
Where practical, actual equipment operation and performance of evolutions 2
will be included.
Quizzes on systems, equipment and procedures are included for evaluation of the trainees' progress throughout the program.
In addition to the program incorporating classroom work on basic fundamentals plus plant systems and equipment, each person will participate in a program at an appropriate simulator.
Candidates apply-ing for an original license with very little experience or technical educational background will participate in the three-week simulator program described in Attachment C.
The intent of this program is to introduce the trainee to all aspects of control room operation so he can gain experience and, therefore, confidence in handling the full spectrum of situations.
It. is expected he will return from this simu-lator program significantly better prepared to handle the duties of a licensed operator.
Those candidates with significant experience or technical education will participate in the one-week program described in Attachment D.
This program reviews significant operations and pro-vides hands-on experience and a means of evaluation of the candidates' knowledge and abilities.
A maximum of four people will participate in a simulator pro-gram at one time as a group.
Two groups of four people may participate at the same time on an overlapping shift arrangement.
Upon returning to the Palisades Plant following the simulator training, each candidate will review general and emergency procedures by way of drills conducted in the control room to refamiliarize them with the Palisades Plant controls.
Manipulation Experience - Prior to applying for a license ex-amination, the candidate shall have actual experience manipulating controls of the Palisades Plant.
Manipulation of controls through five reactivity changes, or significant operations other than reactivity changes as speci-fied in Attachment B, shall be accomplished by each candidate.
.No more than three of the five will be the same manipulations.
At least two dif-ferent manipulations must be undertaken by each candidate.
J
3 NRC License Exam ~ The NRC license exam will be administered upon completion of all phases of the training program.
Applications for license shall include certification by the.simulator operator of satis-factory performance by the candidate in the simulator program
- AM PM 3
AM PM AM PM MON BNP 2 Atomic Models Elements Atoms Molecules Condenser Circulating Water,Cooling Towers B?IP 7 Nucleus*Structure Review to Date.
Isotopes Nucl1des Abundance Makeup Water System BNP 12 Nuclear Fission Nuclear Models.
Fission Reaction Review or Nuclear Reactions Fuel Handling System R02 Neutron Production Analop;y Raising Rabbi ts Maintaining Inventory Accounting Systems Turbine Lube Oil System ATTACHMENT A TUES BNP 3 Atomic Characteristics Weight Avogadro's Number Density Service Water BrlP 8 Nucleus Model Model or Nuclei Chart of the Nuclides Nuclear Reactions Service and Instrument Air System WED BNP 4 Molecules Avogadro's Lav Molecular Density Parts Per Million Fire System BNP 9 Reactions Involving Nuclei Chain *Decay Nuclear Notation Mapping of Reactions Heating, Ventilation end Air Conditioning System BNP 13 BNP 14 Cross Sections Reaction Rates Microscopic Cross Section Neutron Flux Macroscopic Cross Section Re.action Rates Cross Section for Reactor Power
- Molecules Auxiliary Feed System R03 Application of Neutron Production Analogy Rabbits end Neutrons Ileutron Life Cycle Define 4 Factors Generator*Seal Oil System Hydrogen Cooling Isophase Bus Condensate System R04 Ii-Factor Fonnula Reproduction Factor Reproduction Factor Fast Fission Factor Turbine - Gen
- Control System THURS BNP 5 Mass ~d Energy Ea me Binding Energy Mass. Defe'ct Component Cooling Water System BNP" 10 Radioactive Decay Activity Half-Life Decay Lav Spent Fuel Pool System BHP 15 Neutron Spectrum &
Energy Effects Neutro~ Spectrum Cross Sections and Energy Resonances Feedvater System R05
- Ii-Factor Fonnula (p,t)
Resonance Escape (p)
Thermal Utilization (r)
Thermal Utilization Cr)
Main Steam System Extraction.& Heater Drain System BNP 6 Energy Production Energy from Finsion Heat from Fission Pover from Fission BNP Weekly Quiz
\\ Systems Review
& Quiz BNP 11 Radioactivity Graphing Radioactive Decay A Mixture of Nuclides Shielding 'considerat-*
ions BNP Weekly Quiz Systems Review &
- Quiz BNP 16 Neutron Slowing Down Collisions Slowing Dovn Nuclear Physics and Safe Operations B~IP Final Ex11111.
Systems Review'&
Quiz
. R06 Buckling and' Leakage Buckling Concept Buckling Application Neutron I.eak88e RO Weekly Quiz System Review &
Quiz
AM PM ROT Space Dependence Review to Date Pover Distribution Distribution Measurement Chemical and Volume R08 Reactor Control Control Rod Effects Control Rod Worth Poison Competition Control System---------------~
R012 Core Depletion Xenon Behavior Long Term Effects Reactivity Budget Control Room Tech-nical Data Book CP2 Thermodynamic Properties Pressure Temperature Speci fie l!eat Specific Volume Enthalpy Heat of Vaporization
.R013 Startup and Shutdown Sources Sub-Critical Muiti-plication Criticality and Shut-dovn Criticality Predic ~ions CP3 Thermodynamics Steam Tables Energy Work Pover Primary Coolant System..... -----------~
CP1 Pump Characteristics NPSH Centrifugal Pumps Jet Pumps Safety Injection System CP8 Heat Transfer Concepts Conduction Convection Safety Injection System R09 Reactivity Coefficients Temperature Coefficient Other Reactivity Coefficients Pover Coefficient ROlO Reactor Kinetics Neutron Population Neutron Lifetime Period and Pover Control Rod Drive System -----------~
R014 Normal *0peration Reactor Utilization Opera~or Duties Xenon Oscillations End of Life Reactivity Balance' Calculations CPl1 Thermodynamics and Heat Balance Quality and Carryover Calorimeter Plant Heat Balance Plant Heat Balance Calculation CP9 Boiling Heat Transfer Nucleate Boiling
- Boiling Effects Critical l!eat Flux Containment Sprlcy' System Iodine Removal
. R015 Refueling Refueling Fuel Manegel!lent Physics Testing Subcritical Multi-plication Problems 1 Exercises CP5 Heat Balance Efficiency Reactor Heat Balance Efficiency Effects on Efficiency Primary. Coolant System Leakage Calculation CPlO Core Thermal Performance Linear Heat Rate Hot Channel Factors*
Containment' ¥r Coolers ROll Time Dependence and Fission.Prod-ucts Dele,yed Neutrons Reactivity and in-hour Equation Fission Products*
RO Weekly Quiz Syste~s Reviev &
Quiz R016 P.eactor Sat:ety Hazards Safeguards Summary RO Final Exam Reviev CP6 Fluid Flow Pressure Drop Flov Characteristics Flov Measurement CP Weekly Quiz System Reviev &
Quiz CPll Core Thermal Perf-ormance Fuel Cladding Integrity DNBR Safety Limits Operatin?, Limits CP Weekly Quiz Systems Review &
Quiz
9
.AM PM 12 AM PM CP12 Pert'onnence end Control Heat Generation Measure-ment Reactor Control Core Protection Surveillance Testing RP2 Interaction ot' Radia-tion Dece.y-Heutron Production Radiation-Conte:nination Interaction with Matter Process Monitors Area Monitors RPS Detection ot' Radiation Ionization Detection Six Region Curve Palisades Radiation Protection Procedures PC3 Coolant Parameters pH Conduct! vi*ty Dissolved Gases Chemical Control Equipment, Feed Equipment, In Line Monitors CP13 CP14 CP15 CP16 Reactor Materials Fuel and Clad Burn up Reactor. :Vessel Internals Refueling Material NDTT
'l'hennal-Hydraulic Course Revlev Application Pump Heat Absorbers and Coolants Pressurizer-Temp vs Level General Operating ProcedureA ~~~~~~~~~~~~~~~~~~~~~~~
Cold ShutdOll?l to Hot Standby to Plant Shutdovn-100%
Hot Standby 100% Pover Power to Cold Shutdown RP3 Biological Effects Cell Reactions Physiological Effects Contem!nQtion Effects RP9 Misc Detectors, Personnel Monitoring Misc Radiation Detectors Personnel Monitors -
Radiation Personnel Monitors -
Contamination PC4 Chemical Processes Ion Exchange Filtration Evaporation Adsorption RP4 Units Exposure and Dose Activity and Modit)'ing Rate anq Volume Portable Monitors,
RP5 Protect:f.'on Against Radia-tion Time.
~*'.
Distance.~
Shielding Personnel Dosimetry~~~~~~~-..~~~~~~~
RPlO Survey Techniques General Survey Techniques Radiation Surveys.
Contamination Surveys PC5
- corrosion - Types Basic Corrosion Types of Corrosion Sampling Systems RP Final."Exam PC6 Corrosiqn* - Materials Carbon. Steel Nickel-Base Alloys Copper-Base Alloys
_Zfrcale;>y*
ChemicBl Lab Equipment CP Final Exam Procedure Reviev '
Quiz RP6 Protection Against Contami.nation Shielding and Radi-
- ation Work Permits Contamination Pro-tection Protective Clothing RP Weekly Quiz Review 10 CFR 19 Procedures Reviev
& Quiz
~C7 Chemistry Control Equipment Filters Ion Exchangers Filter-Demineralizera*
Evaporato~
PC Weekly Quiz System Reviev '
Qu!z
13 AM PC8 PC9 PClO PCll PCl2 Radiation Effects - I Radiation Effects - II Primary Water Chemistry Boiler Water Chemistry (PWR)
Make-Up Water Radiolytic Decomposition Activation Products Vendor Specifications pH - Phosphate System Clari fi-Radiation Synthests Crud Cycle Chemical and Volume Control.Oxygen cation Fission Products Crud Properties System Carryover Chlorination and Miscellaneous Chloride Softening Solids Deaeration end Feedvater Adsorption Hideout*
Reverse Osmosis Once-through Steam Generator and Electro-dialysis PM Rad Waste Systems PC Final Exam 14 AM ICl
.IC2 IC3 IC4 IC6 e
Basic Electricity Basic Electrical Circuits Measurement Methods Process Instrumentation
?leutron Detection Electrical Circuits Series and Parallel Temperature Pneumatic Detector Applica-Ohm's Lav Circuits Pressure Electrical tions Pwer Amplifiers Flov Pulse-type Detect-Level ion Che:nber.s Current-type Det-ection Chambers Self-pvered Detectors PM Feedvater Control Reactor Control System.
IC5 IC Weekly Quiz System Preosurizer Controls Basic Control Systems Systems Review (Level-Pressure)
Control Concepts Steam Pump end Turbine
- Proportional Control Bypass Control Control Modes 15 AM Neutron Monitoring Data Loggers RPCIC Protective System Reviev Systems Logi c Di a.grams PM Reactor Protection SPI SIAS IC Final Exam System PIP lti AM POP2 POP4 POP5 POPG Procedures, Tecbn1-Nuclear Plant Incidents Trial Examination - l Trial Exlllllination - 2 Trial Exlllllination - 3 cal Specification Decay Heat Quizmenship Reactor Theory Reactor Operation Review Water Hammer Principles or Reactor Fuel Handling and Core (Simulated Orel Exam)
Water Hwnmer Incidents Operation Parameters Features or Facility Design PM Abnormal Occurrence Facility Change Review Review
17 18 19 20 21 22 23 24 25 2G 27 AM PM AM PM AM PM POPlO Trial Examination - 4 Radiation Cont~ol and Safety Radioactive Material Handling, Disposal and Hazards
- POPll Trial Examination - 5 Radiation Protection (simulated oral exam)
Emergency Procedures, Review and Drills POP14 Trial Examination - G General Operating Characteristics Specific Operating Characteristics POP15 Trial.Exmn1nation - 7 Instrumentation*and Control Safety and Emergency*
Systems POPlG Trial Examinat1ron
- 9 Plant Operation (simulated oral exam)
Emergency Procedure Drills (Site Emergency Plan Drill)....:.....-----~--------------------------)
SimUl.ator Orientation System and Instrumentation Review Simulator Program Simulator Program Simulator Program Palisades Refamiliarization Program Plant General Procedures Review and Drill Palisades Refemiliarization Program Emergency ~rocedure Drills Emergency Proaedure Drills Practice Ora~ and Written Exams, Review
.AEC Exams
A.
ATTACin.iENT B Signii'icant Control Manipulations Manual control of the reactor during boration maintaining reactor power.
change required vill be a minimum of dilution or Reactivity
.01% />*
B.
Manual control of the reactor maintaining stable reactor power during a Xenon transient for one hour or more.
Manipulation must be perfonned in the first 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of a transient folloving a paver change of 25~ or greater.
- C.
Change in core reactivity by the operator of 0.1% ~
in less than one hour for any reason utilizing either control rods or boric acid control.
D.
Change of reactor power greater than 10% of t'ull power on one hour or less.
E.
Attendance at plant controls during and immediately following a plant trip from power level greater than 10%
- F.
Operation of the plant controls during any major step in start-up or shutdovn, i.e~,
- 1. Start-up from cold shutdown to hot standby.
- 2.
Critical approach from hot standby to point of adding heat.
- 3.
Turbine generator start-up from hot standby.
It.
Plant loading from synchronization.
- 5.
Plant shutdown from power to hot standby *
- 6. Plant cooldovn from hot standpy.
G.
Control of steam generator levels from synchronization to 15% power including transfer to.auto.
H.*
Manual reactor control from synchronization to 15% power, including transfer to auto *
/
/
e*
ATTACH?.mNT C.
Simulator Training Simulator training will consist of three weeks on the Combustion Engineering Simulator at Windsor, Connecticut.
The time vil1 be spent on demonstration sessions, practice sessions and exercise sessions.
The demonstration sessions will be for the purpose of orientation and familiarization with controls and response of the simulator.
The practice sessions give the students experience in identifying mal:ftmctions and responding to the effects. Exercise sessions are used to evaluate operator ac:tion in response to abnormal.
conditions
- Demonstration sessions will require approximately eight (8) hours to conduct.
Fi~y-two (52) hours will be spent on practice sessions; approximately forty (40) hours in clas_sroom discussion on details of simulator systems, transient analysis ~d *systems overview.
Approximately twenty (20) hours will be spent conducting exercise sessions to evaluate indi Vi dual operator performance.
Palisades operating procedures and control room nomograms, etc.
will be.utilized the maximum extent possible during the simulator training.
\\There differences preclude direct application of Palisades.procedures and/or technical data, the differences will be discussed in.classroom sessions,
. to clarify reasons for such deviations.
~e simulator program will provide, as a minimum, the folloving operational experience for each candidate:
A.
At least tvo reactor start-ups with different initial conditions, proceeding vi th plant start-up to turbine-genera.tor synchronization.
ATTACIIl*iE!fT C Simulator Training (Contd)
B.
At least one plant heatup fi:om cold sh1,ltdovn to point of withdrawal of control rods for critical approach.
C.
At least one reactor and plant cooldmm from hot standby to cold shutdown.
D.
A minimum of ten hours in practice sessions on abnormal conditions or emergency conditions with emphasis on*identi:f'ying the condition
- E.
A mini??lum of twenty hours in responding to abnormal end emergency conditions with emphasis on immediate action.
Trainees wiil be expected to recover from casualty, where possible *.
~......
-I ATTACHMEUT D Simulator Program The simulator training course :for engineers or experienced operators is a one week program.
This program provides approximately thirty-:five hours of hands-on experience on the simulator.
This includes demonstration sessions, practice sessions and evaluation sessions.
Trainees will operate the plant controls under a variety of conditions including transient and emergency conditions.
Evaluation exercises will be limited to reactor startup exercises under different conditions and where practicable, some mal:f'unctions included.
Simulator orientation classroom work will be accomplished just prior to reporting to the simulator, to minimize time needed to acquaint trainees with simulator control room, etc.
Palisades technical data and procedures will be utilized during simulator exercises to the extent practical. Differences will be pointed out and discussed as they are encountered *
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