ML20134N094
| ML20134N094 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/30/1981 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Collins P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8509050002 | |
| Download: ML20134N094 (11) | |
Text
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INFO COPY PHil_ADELPHIA ELECTRIC COMPANY %
2301 MARKET STREET Q 'R &
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f P.O. BOX 8699 PHILADELPHIA. PA.19101 RECElvED'
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ELEC teeC PAODUC,H)N April 30, 1981 y,,
,t 7, Dm Re: Docket Nos. 50-P77 50-278 Mr.
P. F. Collins Operntor Licensing Branch Office of Nuclear Reactor Regulation US Nuclear - Regulatory Commission l
Washington, DC 20555 dgb
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SUBJECT:
Revised Peach Bottom Training Program 30g
Dear Mr. Collins:
The Peach Bottom training and qualification program was revised to meet the requirements delineated in a letter from Mr.
11. R. Denton of the HRC, dated March 28, 1980, to All Power Reactor Licensees.
Portions of this program were recently reviewed on-site with an NRC inspector.
Subsequently, the Operator Licensing Branch, in a phone conversation on November 21, 1980, requested the transmittal of additional information concerning:
1.
Licensed NRC Operator Requalification Program 2.
Replacement Training for Licensed Operators and Licensed Senior Operators Enclosed are descriptions of these training programs.
The training programs described may be revised periodically, to the
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extent permitted by the NRC regulations, so as to adapt the
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program to the individual needs of the trainees.
Portions of the license training described may be of little.value to candidates who are graduate engineers and therefore may be modified in recognition of their academic background.
Should you have any questions regarding this matter, please do not hesitate to contact us.
Very truly yours, VCB/klm Ongnal signed by S.13. DALTROFE j
Enclosure becs V. S. Boyer E. J. Bradley V. T. Ullrich J. S. Kemper M. J. Cooney
'W. M. Alden/W. C. Birely J. W. GallaC er R. H. Moore h
//
8509050002 810430
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PHILA DELPHI A ELECTRIC COMPANY PE ACH BOTTOM ATOMIC P0'JER STATION DELTA,PENNSYLVANTA LICEMSED HRC OPERATOP REOUALIFICATION PROGRAM This section describes the requalification program for licensed operators and licensed senior operators at the Peach Pottom Atomic Power Station.
1.
SCHEDULE The requalification program is conducted on a two year cycle.
2.
LECTURES The requalification program includes preplanned lectures given on a regular and continuing basis throughout the license period and includes those areas where annual operator and senior operator written examinations indicate the coverage is needed.
A minimum of nine lectures is scheduled annually and a minimum of 18 lectures for each cycle.
The lecture program year will be January through October with lectures normally scheduled at the rate of two per six week cycle.
Should plant requirements preclude holding to the schedule, lectures will be rescheduled so a minimum of nine are accomplished per year.
Attendance requirements at the lectures will be determined by the annual written examination as described in the section titled
" Evaluations".
The Jectures cover the fo11owin6 topics:
a.
Theory and principles of operation b.
Features and facility design
,,c.
General and specific plant operating characteristics d.
Pl ant instrumentation and control systems 0.
Plant protection systems f.
Engineered safety systems Normal, abnormal, and emergency operating procedures g.
h.
Radiation control and safety 1.
Technical Specifications j.
Applicable portions of Title 10, Chapter I, Code of Federal Regulations k.
Discussions concerning special plant tests or programs such as refueling 1.
Heat Tr ans fer, Fluid Fl o w, Thermodynamics and Mitigation of accidents involving a degraded core Training aides such as video tape, transparencies, and films may be used to supplement the scheduled lecture series.
Page 2 Individual study is encouraged and training aides may be used to augment the effectiveness of individual study.
3.O?l-THE-J0P TRAINING Each licensed operator manipulate equipment and reactor controls within his license period.
Each senior licensed operator direct the activities of individuals or manipulate controls within his license period.
All licensees participate in simulator programs as part of the requalification progr am.
The following control manipulations and pl ant evolutions are utilized for meeting the required reactivity control manipulations.
The starred (') items are performed on an annual basis; the remaining items shall be performed on a two-year cycle.
Those control manipulations which are not performed at the plant may be performed on a simulator.
Cr edit for these activities are limited to one or two operators per forming the task and one or two senior operators engaged in directing the operations.
'1. Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
- 02. Manual control of feedwater during startup and shutdown.
'3. Any significant (>107) power changes in a manual rod control or recirculation flow.
'4.
Loss of cooling including:
a.
inside and outside primary containment b.
large and small, including leak-rate determination.
- 85. Loss of core coolant flow / natural circulation.
- 6. Loss of all feedwater ( normal and emergency).
- 07. Plant shutdown.
B.
Loss of instrument air.
9.
Loss of electrical power and/or degraded power sources.
- 11. Loss of service water and emergency service water.
12.. Loss of shutdown cooling.
- 13. Loss of component cooling system or cooling to an individual component.
Page 3 14 Loss of normal feedwater or normal feedwater system failure.
- 15. Loss of protective system channel.
- 16. Mispositioned control rod ( s) or rod drops.
- 18. Conditions requiring use of standby liquid control system
- 19. Fuel cladding failure or high activity in reactor coolant or off-gas
- 20. Turbine or generator trip.
- 21. Mal fur.ction of automatic control syst em( s) which affect reactivity.
- 22. Malfunction of reactor coolant pressure / volume control system.
- 23. Reactor trip.
-24 Main steam line break (inside or outside containment).
- 25. !!uelerr instr umentation f ail ur e( s).
Each licensed operator and senior licensed operator demonstrate, within his license period, understanding of the operation of apparatus and satisfactory knowledge of operating procedures in the area for which he is licensed.
This requirement is satisfied by actual operation, or oral discussion, or use of an applicable simulator.
Training while on shift is specified by the Training Coordinator and may include reviews of:
Procedures and changes to procedures.
a.
b.
Technical Specifications and changes to Technical Specifications.
c.
Plant Modi fi ca tio ns.
d.
Plant experiences.
e.
Instr um ent a tion.
f.
Plant systems and _ their operations.
g.
Health Physics.
h.
Reactor Physics.
Training is specified by means of a form letter Assignments may include handouts such as new or revised procedures, plant experiences, reading assignments, and the use of training aids.
Information from NRC Operating Experience Reports and other sources such as plant upset reports which are determined to be pertinent to operator training are attached to the form letter as means of disseminating the information to interested personnel.
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Par,e 4 Similar information which is pertinent but of lesser importance may be posted on the ti aining bulletin board.
4 EVALUATIONS Annual written examinations are given to provide a basis for deternining operator at cas in which retraining is needed. knowledge and also to assist in determining The examinations are operationally oriented and modeled on NPC written examinations.
Operators scoring atave 80" in all sections are not required to attend requalification lectures.
An operator who is evaluated at less than 90" in a section is required to participate in requalification lectures in that 'section.
An operator who is ev al uated at less than 80% on the overall examination or less than 70% in any section will be placed in an accelerated review program.
In addition, an operator who is evaluated at less than 80% on the overall examination or less than 70% in any section is sc hed ul ed for an oral examination to determine the necessity for removing accelerated review.that operator from his licensed shift duties during the the review program untilWritten re-evaluations are made following satisfactory performance is demonstrated by scoring 80" or greater on the overall written test and/or 70%
or greater in each section.
applicable subsequent requalification lectures.The operator also participate in Each operator and senior operator participates in an annual cral examination evcluation with a designated staff member.
evaluation includes actions taken during actual or simulated Th e abnormal and emergency conditions.
If the overall performance of the operator is unsatisfactory, he is placed in a review program to correct the deficiencies noted.
assist in the oral evaluation.
A simulator may be used to Written quizzes are administered at the conclusion of each lectures series session.
at the lecture, a grade less than 807 indicates a need forFor those whose atte cdditional training in that subject.
is under the direction of the training supervisor or shiftThe supplementary training supervision.
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Any inactive licensee, who has less than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of participation or observation of control rod operations over four month period,
a demonstrate that his knowledge andis given an oral examination evaluation to are satisfactory.
understanding of the facility Licensed staff members are required to have a minimum of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of participation in control room operations over a four month period.
function or actual reactor operations.This participation may include a senior su Each candidate is administered an oral examination by the PP APS Certification Board to determine their competency.
Upon making a A
Page 5 determination, the Board recommends to the Station. Superintendent whether or not the candidate should be recommended for l'R C license renewal.
The results of the certification Board is used by the Vice President - Electric Production for his use in certifying individuals for re-license applications.
5.
REC 0FDS Each operator and record book his record of plant reactivity changes. senior operator keeps curr The responsible shift supervisor verifies these records by initialing them.
The Shift Superintendent is responsible to see that an individual's participation in a shift training session is recorded.
Records are maintained of the requalification program to document each licensed operator's and senior operator's participation.
The records contain copies of written annual examinations administered, the answers given by the licensee, results of the evaluation and documentation of additional training in areas in which the operator exhibited deficiencies.
Af ter an NRC - NRR audit, copies of audited individual examination answers may be destroyed.
6.
_00ALITY ASSUR AUCE The lesson plans, instructions, procedures, and drawings used in the training program are approved by the designated training.
supervisor of Assurance of quality of the training is the responsibility of the Engineer Technical.
Audits of the requalification program Electric Company Quality Assurance Division.are made by Philadelphia I
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PHILADELPHIA ELECTRIC COMPANY PE ACH BOTTO'1 ATOMIC POWER STATTOM DELTA, PENNSYLVAMIA REPLACEMENT TPAIMING FOR LICENSED OPERATOPS AMD LICENFED SENTOR OPERATORS This section describes the training program being conducted at the Peach Bottom Atomic Power Station for NRC license candidates.
During all phases of the described program the student's progress is monitored by oral questioning and periodic written quizzes.
PHASE I PRELIMINARY INTERVIEWS Operator. licensing candidates who participate in the courses are interviewed by a qualified instructor.
Purpose of these ind iv id ual interviews is to:
a.
Identify common areas of weakness such that course modifications may be made.
b.
Identify candidates who may need more work and/or attention during subsequent training.
c.
Introduce candidates to the NRC licensing process.
PHASE II ACADEMIC REVIEW Formal classroom lectures are presented 'in the areas of Ma th em atics, Physics, and Fundamentals of Heat Transfer.
The objective of the review is to provide the student with a basic.
understanding of the scientific and engineering principles of reactor plant operation.
The training program will vary according to the trainees academic background.
Normally, three weeks of lectures are scheduled, one week per topic area.
t e
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Page 2 A.
Week 1 Math em ati c s Topics Introduction Basic Numbers Signed Numbers Algebraic Operations Problem solving Algebraic Equations Word Problems Factoring Fractional Equations Systems of Equations Graphing Ex ponents, Powers, Roots Scientific Notation Radicals Ratio and Pro portion Logarithms and Logarithmic Equations Trigonometry Review and Exam B.
Week 2 Physics To pic s Introduction Definitions Units and Unit Conversion Atomic Structure Mass - Energy Equivalance Binding Energy Nuclear Stability Radiation Radioactivity Nuclear Reactions Nuclear Cross Sections Properties of Radiation Fission Process and Fission Energy Neutron Behavior Neutron Multiplication Reactivity Introduction of Coefficients BWR Operations Reactivity Balances Reactor Period Suberitical Multiplication Fission Product Poisons Review and Exam
Page 3 C.
Week 3 Thermodynamics To pic s Review of Physical Science Introduction to Thermodynamics Fundamental Concepts and Darinitions Thermodynamic Systems Work and Energy Property of Matter Processes Cycles Heat First Law of Thermodynamics Aplication of the General Energy Equation Second Law of Thermodynamics Power Plant Cycles Carnot Cycle Rankine Cycle Fundamentals of Fluid Flow Bernoulli's Equation Rev iew, Summary, Exam PHASE III PEACH BOTTOM TECHt! OLOGY This training includes classroom 1ectures on PBAPS nuclear steen supply and balance-of-plant systems and their procedures.
Technical Specifications are also addressed.
Lectures on plant systems are presented in adequate depth such that the students can understand overall operation of the plant.
Where appropriate, plant and/or control room tours are used to augment classroom presentation.
This phase of training is normally scheduled to last R weeks.
Review sessions and quizzes are scheduled where appropriate.
A.
Week 1 Topics Introduction to course and Technical Specifications Reactor Vessel Construction Reactor Vessel Internals Nuclear Fuel Reactor Vessel Instrumentation l
Reactor Recirculation Systems Recirulation Flow Control CRD Mechanism and Hydraulics 1
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Page il Reactor Manual Control System Rod Worth Minimizer Rod Sequence Control System Primary Containment Containment Atmosphere end Control Dr ywell Cooling Containment Atmosphere Dilution System Prim ary Containment Isolation System Plant Tour s, Sel f Stud y, Review, Exam B.
Week 2 Topics Principles of Detector Operation SRM LPRM IRM APRM Rod Block Monitor -
TIP Reactor Protection System Secondary Containment Reactor Puilding Ventilation Standby Gas Treatment System Self Stud y, Plant Tours, Review, Ex am C.
Week 3 Topics LOCA Scenario HPCI ADS Core Spray LPCI RHR (Excluding LPCI Mode)
HPSW Emergency Cooling Towers RCTC Standby Liquid Control System Plant Tours, Review, Exam D.-
Week 4 Topics Reactor Building Cooling Water Pain Steam and Pressure Relief Extraction Steam (including Feedwater Heaters, Vents, and Drains)
Auxiliary Steam i
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Page 5 Condensate Condensate Demineralizers Solid Radwaste Liquid Rad wa ste Condensate and Refueling Storage and Transfer Feedwater Feedwater Control System Circulating Water and Cooling Towers Plant Tours, Sel f Stud y, Review, Ex am E.
Week 5 Topics Reactor Vater Cleanup System Condensate Air Removal Off-Gas and Recombiner Main Turbine and Auxiliaries MTLO EHC Hydraulics EHC Logic and control Service Water Turbine Building Cooling Water Fire Protection Make-up Water Treatment Plant Tours, Self Study, R ev ie w, Exam F.
WEEK 6 Topics Main Generator and Generator Auxiliaries Generator Seal Oil Generator Stator Cooling Generators H2 Cooling Main Power Distribution 13.2 KV and above TRW System
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AC Electrical (4160 VAC)
AC Electrical (430 and below)
DC Electrical (250, 125, 24 VDC)
Emergency Diesel Generator Emergency Service Water Plant Tours, Self Study, Review, Exam
.G.-
Week 7 Topics Fuel Handling Equipment Fuel Pool Cooling and Cleanup Plant Air System E
PeSe 6 Area Radiation Ponitoring Process Radiation Ponitoring Process Computer Leak Detection System Plant To urs, Peview, Self Study, Exam H.
Week P To pic s Pre-Simulator Review Basic Reactor Theory Reactor Startup Procedure Reactor Transient Response PH ASE IV SIMULATOR HOT CERTIFIC ATION Each candidate participates in a two week (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) hot certification simulator course.
This course is one-half classroom lecture and one-half simulator operation.
All phases of plant operation are covered with emphasis placed on normal plant operation.
Each candidate will perform ten or more reactivity manipulations during the program.
Additionally,each candidate will perform a reactor startup demonstration late in l
the course that will allow the candidate to take an NRC exam without performing the reactor startup on the Peach Bottom plant itself.
PHASE V PLANT FUNDAMENTA'.S AND HEAT TR At'SFER Training includes normally four weeks of classroom lectures.
Three weeks include topics on Reactor Theory, emphasis on Reactor and Plant Transients, Core Operating Characteristics, Plant Operating Characteristics, Health Physics, and Radiation Protection.
One week of lectures includes BWR Heat Transfer,
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Fluid Flow, and Thermod ynamics.
All subjects are presented at a depth adequate for overall understanding and appropriate for NRC Licensing at the SRO level.
A.
Week 1 BWR Operating Characteristics tie a t Transfer Core Thermal Hydraulics i
Safety Analysis Accidents l
Safety Analysis Malfunctions l
Coolant Chemistry l
Technical Specifications I
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h Page 7 Self Study, Peview B.
Week 2 Ilealth Physics and Radiation Protection Health Physics Fundamentals Radiation Protection Procedures Site Fmergency Plan and Procedures Radiation Survey Equignent Env ironmental Technical Specifications
[j Respiratory Protection Program Applicable 10 CFR's Self Study, Review C.
Veek 3 Reactor Theory Basic Theor y Fev iew Neutron Sources Suberitical Multiplication Delayed Neutrons and Delayed Neutron. Fractions Reactor Period Reactivity Coefficients Fission Production Poisons Rod Worth D.
Veek 4 Heat Transfer Fundamentals Ile at Transfer Mechanisms 1.
Conduction 2.
Convection 3.
Radiation Heat Transfer in Peactor,' Elements Convection Laminar Flow Turbulant Flow e
BWR Heat Transfer Pool-Boiling Curve Heat Transfer Regimes in a BWR BWR Thermal Hydraulics Friction Pressure Drop in a Poiling Channel Acceleration Pressure Drop Core Orificing Ouality and Void Fraction Quality and Void Fraction in a Flow System J
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Page 9 t
Critical Po wer Transition Poiling Critical cuality The GEXL Correlation Critical Po wer Linear Heat Generation Rate L-LHGR Peaking Factors f
Average Planer Linear Heat Generation Pate APLHGR Reactor Heat Balance u
Simple Heat Addition Heat Input and Output Flowing Systems BWR Heat Palance w
PHASE VI EXAMINATION AMD GUIDED SELF STUDY A short written ' nd oral examination is conducted to assess a
students progress and to guide them in their study.
The remainder of the week is spent in guided self stud y.
PH ASE VII SHIFT 03SERVATION The trainees are assigned to a 12 week on-shif t period to familiarize them the layout and normal routines that take place f
in the control room.
The instructor meets with the students cpproximately once per week to guide their study and activities, to give them assignments and check-off sheets, and to monitor their progress.
' PHASE VIII CONTROL OR MITIGATION OF AM ACCIDENT IN WHICH THE CORE IS SEVERELY DAMAGED, AND SELECTED REVIEW I
s,' A 4
This phasy lasts three weeks and includes selected topics for review, ared training in the use of installed plant systems to control or mitigate an accident in which the core is severly d am aged..
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Page 0 A.
Reactor Vessel Instrumentation 1.
Operation of Level Detectors 2.
Reactor Level Instr um ent ation Ranges
- 3. Reactor Vessel Level Initiation Setpoints 4
Level Instrumentation Failure Response
- 5. Cautions related to Reactor Vessel Level In s t r um ent a ti on B.
Neutron Monitoring System
- 1. General Information - Power Level Ranges, Fission Chambers Various Sensitivities, Sense Thermal Neutrons
- 2. Source Range Neutron Vonitoring
- 3. Intermediate Range Neutron Monitoring 4
Lo cal Power Range Neutron Vonitoring
- 5. LOCA Effects on Neutron Monitoring C. Alternative Measurements
- 1. Measur ement Correlations 2.
Hydrogen Generation
- 3. Core Damage Effects on Coolant Ch emistr y D. Radiation Levels and Cladding Failure 1.
TMI Incident l
- 2. Containment Radiation Levels
- 3. Secondary Containment Radiation Level s 4
Cladding Fragmentation PHASE IX GUIDED SELF STUDY One week of Guided Self Study is scheduled in preparation and review for_ Audit Ex aminatio ns PHASE X AUDIT EXAMINATIONS Both written and oral audit examinations are conducted.
These exams parallel the NRC licensing exems in scope, depth, and length.
A Four hour walk through is administered to each candidate.
This oral examination also parallels the NRC. oral exam.
A report is written regarding the results of the audit exams and the suitability of each candidate for taking the NRC exam.
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Page 10 PHASE XI REVT Ek' COURSE This is the final phase of training prior to NRC licensing.
A five day formal classroom review is presented by the instructors
' CERTIFICATION BOARD Each. candidate for NRC licensing is examined by a Certification
.Y Board.
The purpose of the Board is to determine the competency of each candidate for an MRC license.
In addition to reviewing the candidate's training record, the Board will administer an cral examination to assist in the determination of competency.
Three of the four board members are members of the plant' staff with SLO licenses.
The fourth member is the training coordinator or-his representative.
Upon making a determination, the Poard Will recommend to the Station Superintendent whether or not the candidate should be recommended for examination by the NRC.
The results of the Certification Poard will be used by the Vice President - Electric Production for his use in certifying individuals for NRC license applications, l
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