ML20087J647
| ML20087J647 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/31/1984 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20087J642 | List: |
| References | |
| NUDOCS 8403230021 | |
| Download: ML20087J647 (50) | |
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DETROIT EDISON COMPANY i
FERMI 2
' NRC LICENSED OPERATOR TRAINING REQUALIFICATION PROGRAM 4
ADMINISTRATOR'S GUIDE l
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Jan. 1984 NT/R199/1.0 022384 8403230021 840314 .
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i I CONTENT TOPIC SECTION Introduction (To Guide) 1 Purpose and Requirements 2 Training Course Outline and Objectives 3 Conduct of Course 4 l
Revision 0 Jan, ~ 1984 -
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INTRODUCTION Revision 0 Jan, 1984
INTRODUCTION The Administrator's Guide is designed to provide the training administrator with course administrative requirements, and guidelines necessary to:
o Implement consistent training practices o Plan and administer the required training o Avoid scheduling conflicts o Initiate proper documentation o Properly evaluate the course The Administrator's Guide is also concerned with providing the Adminis-trator with the means to ensure the objectives of the course are covered.
This guide is furthermore designed to ensure regulations, standards and procedures are complied with.
i The guide covers suggested training aids, strategies, and methods used to conduct the course. The intent here is to provide the Administrator with information that would be helpful to the instructor.
Records must be initiated by the Administrator to properly document all information pertinent to this course. Records maintained for this course will comply with regulations and standards (Federal & Company).
General guidelines are written to provide direction for the Administrator and to facilitate the implementation of this course. The guidelines are not absolute policy. They may be changed and/or modified as experience dictates.
The "Requalification Training Program" will be addressed as "the continuing training program" within the text of this Administrator's Guide.
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1.1 Revision 0 Jan, 1984
PURPOSE AND REQUIREMENTS Revision 0 Jan, 1984
PURPOSE Subject NRC Licensed Operator Requalification For Nuclear Supervising Operators, Nuclear Assistant Shift Supervisors, Nuclear Shif t Supervisors, Selected Plant Staff.
Pre-Requisite (s) Holding a Current NRC License for Fermi 2 or Selected by Plant Management to attend.
Purposes (s) The purpose of this course is to ensure that the knowl-l edge and skills for safe operation of Fermi 2 are maintained at a high level of competence. This program includes all NRC required training as well as those
! courses deemed necessary by Detroit Edison.
This course utilizes the knowledge gained in previous required NRC License training courses, in conjunction with actual application on the Plant Simulator to bet-ter understand the detailed operations of the plant during normal, abnormal and emergency plant operations.
The course also emphasizes aspects of theory and plant operation, not normally used, to ensure operator familiarity should the need arise to utilize this info rmation. This program will incorporate changes in Plant Operation or System Operation caused by regulatory changes, design changes, or industry wide
" lessons learned" operational changes.
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, REQUIREMENTS NRC Licensed Operator Requalification Program Purpose The purpose of this section of the Administrators Guide is to provide direction on Laplementation and establish requirements for continuing training of licensed operators (RO, SRO, SRO-R) identified on the Licensed Operator Training Program Description. 1 Description This section of the Administrator's Guide provides a description of the continued training program for licensed operators.
Definitions Course: A major subset or breakdown of a program dealing with similar content and/or similar objectives (e.g., Systems Training).
Inactive Licensed Personnel: Means those licensed personnel who- have not been actively per-forming the functions of an operator or 4
senior operator for a period of four months i
or longer.
Licensed Staff member: Means any person who main-tains an operator's or senior ' operator's license for the purpose of providing backup capability to the normal operating staff.
Such persons may include, but are not limited to, the Assistant Superintendent, the Opera-tions Engineer, the Reactor Engineer, and Nuclear Training Operations and Simulator instructional staff.
On-Shift Discussion: On-shift discussions may include review of procedures, discussions of significant LER's and/or other specific material assigned by the training staff.
Program: (curricula, prescription, traini- sth)
The total training a candidate receives _ co become or remain qualified as a job incumbent (e.g. , NRC License Candidate Training Program).
Reactivity Control Manipulations: Control !
manipulations which meet the requirements of one or any combination of the following are considered as acceptable reactivity control manipulations:
2.2 Revision 0 Jan, 1984
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Definitions o Any plant or reactor startup, to include (cont'd) a range such that reactivity feedback from heat addition is noticeable.
o Any temperature change, heatup or cool-down, 100*F.
o Plant or reactor shutdown.
o Plant shutdown or reactor hot standby.
o Control rod sequence changes.
o Shutdown margin check.
- o Control rod scram insertion time tests.
o Any reactor power change of 10% or greater including test of equipment where load changes are performed with control rods, " load selector" of EHC system in manual or where the recircu-lation system is in manual speed control.
o Plant and reactor operations that in-volves emergency or transient procedures where reactivity is changing.
o Refueling operations where fuel is moved in the core.
o See Addendum A. l Reactor Operator (RO): An NRC licensed individual who manipulates the controls of a facility.
Senior Reactor Operator (SRO): An NRC licensed individual designated by a facility licensee under Part 50 of the Code of Federal Regu-lations Article 10 to direct the licensed l activities of licensed operators.
SRO-R: Identifies those candidates that hold an NRC Operator License restricted from full performance of Licensed Activities or limited to those activities associated with refueling ope rations.
Responsibility The Supervisor, Nuclear Training and Qualifica-tions--Operations and Simulator shall be respon-sible for insuring proper implemet.;ation of the continuing training program described in this Administrator's Guide.
2.3 Revision 0 Jan, 1984 1
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Applicability All personnel who hold an NRC license and are required to maintain that license shall partici-pate in the Licensed Operator Continuing Training Program. Individuals who hold an SRO-R shall participate in those portions of the continuing training program appropriate to the duties they perform.
Program Description The Continuing Training Program for all licensed (Required Topics) operators shall consist of the following topics:
o Thermal Science Review.
o Selected Systems Review.
o 10CFR19, 20, 50, 55 and 100.
o ' Operational Characteristics and Procedures.
o Reactor Theory.
o Technical Specifications o Procedure Revisions Review.
o Recent Operating Experience Document Review.
o Mitigating Core Damage.
o Fuel Handling Review.
o Radiation Worker.
o Respirator.
o EF2 Orientation.
o Safety Electric Switch 480V (SAFLEX 480).
o Task Required Courses.
Procedure Review Each licensee shall review on an annual basis, the abnormal and emergency operating procedures.
Procedure review can be completed by utilizing any of the following methods:
o Actual Performance under abnormal or emer-gency oparating conditions.
o Simulated walkthrough of the procedural steps necessary to cope with the situation.
o Brief lectures conducted by licensed individuals.
1 o Simulator Drills.
o Continuing Training topic presentation.
On-the-Job Training All licensed personnel shall participate, to the extent practicable, in Reactor control manipula-tions and plant evolutions to demonstrate - their skill and familiarity with plant systems.
2.4- Revision 0 Jan, 1984
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l On-the-Job Training o Each licensed Reactor Operator shall manipu-(cont'd) late, and each Licensed Senior Reactor Opera-4 tor shall manipulate or direct the manipu-lation of the Reactor or Simulator controls to produce reactivity changes during the 2
, year term of license.
o Each licensed individual shall perform or direct the performance of the control manip-ulations and plant evolutions listed in Addendum A. Manipulations are to be performed in the plant or on the simulator as practicable.
I Procedure, Design, All licensel personnel shall be kept cognizant of Facility Changes Fermi 2 design, procedure and facility changes, appropriate to their license, using ona of the following methods:
o Brief lectures conducted by cogaizant licensed supervisory personnel.
o Required Reading List.
o Written communique to each licensed individual.
o Continuing Training Program.
Additional Persons holding NRC licenses, but in the IMACTIVE Requirements STATUS, shall be refamiliarized with plant sys-tems, procedures, and operating events. Upon
, completion of the refamiliarization program, the licensee will be examined prior to resuming licensed duties. The refamiliarization program shall consist (as a minimum) of the following.
o Procedure Changes o License Changes o Plant System Modifications I
o Plant Incidents o Significant License Event Reports o Control Room Orientation The completion of the refamiliarization program shall include written and oral examinations to insure that the licensee is up-to-date and -
familiar with the plant. Successful completion is demonstrated by 'a score of- 80% on the written -
- exam and a ~ pass grade on the oral exam. _ The Supervisor, Nuclear Training and Qualification--
Operations and Simulator shall document the satisfactory completion of _ the refamiliarization 2.5 Revision 0 Jan, 1984 1
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I Additional program and certify the licensee. The NRC shall '
Requirements (cont'd) be notified of this fact. NRC approval of the I
certification is required prior to the resumption of Licensed Duties.
Unsuccessful completion of the refamiliarization program shall require the individual to receive additional training in deficient areas as indi-cated by the weak areas on the written and oral exams.
Administering Three types of examinations will be used in the Examinations continuing training program. For certification by the NRC, it is necessary to ensure that individual performance can be determined and properly docu-mented with each type examination. The methods of examining and administration requirements for each are as follows:
o Written - All written examinations will be taken under the supervision of a proctor.
The proctor will be present at all times during the examinations. Only materials required for use with the examination will be present. The proctor will not answer examination questions nor allow anyone to answer or make available the answer to a question.
o Oral - Oral examinations can be administered at any location where the required materials are available. The person giving the oral examination is responsible for ensuring that the individual being evaluated is working independently-and not using unauthorized material to assist in answering questions.
o Performance - Performance will be monitored in the control room and/or while operating the simulator. The evaluctor is responsible for documenting the individual's ability to operate equipment under normal, abnormal and emergency conditions.
Evaluation All licensed personnel shall be examined at the frequency noted below.
Examinations will be conducted at the end of each cycle. A minimum grade of 80% is required on each cycle examination.
2.6 Revision 0 Jan, 1984
Evaluation A grade of less than 80% on any Cycle examination (cont'd) shall require that individual to be rescheduled for that cycle at the. earliest possible date or to
. upgrade knowledge level in the deficient areas on i a program of directed individualized instruction
! and be re-examined to'the original criteria.
a l Each licensed individual shall take an annual exam. A minimum overall grade of 80% with all individual category grades greater than or equal to 70% is required.
l Operational examinations shall be administered to il each licensed individual on an annual basis at an appropriate time during any of the cycles. The operational exam will be evaluated on a pass / fail 7 basis.
Each licensed individual shall be evaluated by-his/her immediate supervisor on an annual basis.
This evaluation should address such areas as performance during abnormal evolutions and routine performance of license . activities.
A licensed individual who receives an overall grade of less than 80% on the annual exam, or receives a grade of less than 70% on any category of.the. annual exam shall be immediately_ relieved of all licensed duties and placed in an accelerated requalification program.
o An individual who is relieved of his licensed duties shall be so advised by plant
, management.
o He may return to his licensed duties-4 following successful completion of those areas noted as failures on ' the written exam.
Completion of this accelerated j requalification training shall require a
- grade of not less than 80% on examination given over the' area (s) noted as failure (s).
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4 ADDENDUM A l
EF2 Requalification Control Manipulations The following is a list of the required Reactivity Control Manipulations for - requalification. The starred items shall be j performed on an annual basis; all other items shall be performed over
- a two year period.
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- 1. Plant or reactor startups to include a range that reactivity feedback i from nuc?. ear heat addition is noticeable and heatup rate is established.
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- *2. Plant Shutdown.
- 3. Manual control feedwater during startup and shutdown.
- 4. Any significant (>10%) power changes in manual rod control or recirculation flow.
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- 5. Any reactor power change of 10% or greater where load change is performed with load limit control.
- 6. Loss of coolant including:
- a. inside and outside primary containment
- b. large and small, including leak-rate detarmination
- 7. Loss of instrument air (if simulated plant specific).
- 8. Loss of electrical power (and/or degraded power sources).
- 9. Loss of core coolant flow / natural circulation.
- 11. Loss of service water if required for safety.
- 12. Loss of shutdown cooling.
- 13. Loss of component cooling system or cooling to an individual component.
- 15. Loss of all feedwater (normal and emergency).
- 16. Loss of protective system channel..
- 17. Mispositioned control' rod or rods (or rod drops).
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- 18. Inability to drive control rods.
- 19. Conditions requiring use of Standby Liquid Control system.
- 20. Fuel cladding failure or high activity in reactor coolant or offgas.
- 21. Turbine or generator trip.
- 22. Malfunction of automatic control system (s) which affect reactivity.
- 23. Malfunction of reactor coolant pressure / volume control system.
- 24. Reactor trip.
- 25. Main steam line break (inside or outside containment).
- 26. Nuclear instrumentation failure (s).
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2.9 Revision 0-Jan, 1984
7 TRAINING COURSE OBJECTIVES l
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COURSE OUTLINE I. Cycle 1 A. Selected Systems Review, 500 03 15 00
- 4. Automatic Depreesurization System
- 6. Core Spray B. Technical Specifications C. Procedure Revision Review D. Recent Operating Experience Document Review
- 1. LER's
- 2. SOER's
- 3. Nuclear Network
- 4. DCP's
- 5. FSAR Changes E. Reactor Theory, 450 01 10 00 F. Simulator Operations, 500 09 01 00 G. EF2 Orientation, 550 05 02 00 II. Cycle 2 A. Selected Systems Review, 500 03 15 00
- 1. Reactor Pressure Vessel and Internals
- 2. Reactor Pressure Vessel Instrumentation 31 Revision 0 Jan, 1984
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COURSE OUTLINE (cont'd)
'3. Reactor Building Closed Circulating Water / Emergency Equip-
. ment Cooling Water.
- 4. Primary Control and Isolation Control
- 6. Control Rod Drive Mechanism and Control Rod Drive Hydraulics
, ,B.;) Technical Specifications C. Procedure Revision Review D. Recent Operating Experience Document Review
- 1. LER's 1
- 2. SOER's
- 3. Nuclear Network
- 4. DCP 's
. 5. FSAR Changes E. Simulator Operations, 500 09 01 00 F. SAFLEX (480), 450 01 11 00 III. Cycle 3 A. Selected Systems Review, 500 03 15 00 3 1. Reactor Water Cleanup System
- 2. Rod Block Monitor 3.- Rod Sequence Control System
- 4. - Reactor Manual Control System
- 5. Rod Worth Minimizer ,
- 6. Recire. System and Flow Control
- 8. Control Center Heating, Ventilation and Air Conditioning 3.2- Revision 0 Jan, 1984 1
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i COURSE OUTLINE (cont'd)
B. Technical Specifications C. Procedure Revision Review -
D. Recent Operating Experience Document Review
- 1. LER's
- 2. SOER's
- 3. Nuclear Network i
- 4. DCP 's
- 5. FSAR Changes E. Reactor Theory, 450 01 10 00
- 1. Review Problem F. Simulator Operations, 500 09 01 00 G. Task Required Course
- 1. Damage and Rescue, 500 04 18 00 IV. Cycle 4 l A. Selected Systems Review, 500 03 15 00
- 1. Diesel Generators
- 2. Main Steam
- 3. Off Gas
- 4. Main Turbine Control
- 5. Main Generator
- 6. Feed and Condensate
- 7. Remote Shutdown *
.i' B. Technical Specifications C. Procedure Revisions Review I
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COURSE OUTI.INE (cont'd)
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D. Recent Operating Experience Document Review
- 1. LER's
- 2. SOER's
. 3. N'aclear Network
- 4. DCP's
- 5. FSAR, Changes -
E. Fuel Hhndling Review, 500 03 21 00 F. ' Simulator Operations, 500 09 10 00 V. Cycle 5 -
A. Selected Systems Review; 500 03 15 00
- 1. Electrical Distribution
- 2. Fire Protection-
- 3. Reactor Protection System , --
- 4. Process Radiatior. Monitoring System and Area Radiation Monitoring System
- 5. Containment Gas Control (Inerting, Venting and Purging)
B. Operational'CharacteEistic and Procedures C. Technical Specific 5tions D. Procedure Revisions Review .
E. Recent Operating Experience Document Review
- 1. LER's.
- 2. SOER's
- 3. Nuclear hetwork
- 4. DCP's -
5 PSAR Changes. ,.
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COURSE OUTIJ.NE (cont'd) 1 F. Reactor Theory, 450 01 10 00
- 1. Review Problems G. Simulator Operations, 500 09 10 00 VI. Cycle 6 A. Mitigating Core Damage, 500 08 10 00 B. 10CFR19, 20, 50, 55 and 100, 500 10 02 00 C. Thermal Science Review, 500 01 12 00 D. Technical Specifications E. Procedure Revisions Review F. Recent Operating Experience Document Review
- 1. LER's
- 2. SOER's
- 3. Nuclear Network
- 4. DCP's
- 5. FSAR Changes G. Simulator Operations, 500 09 01 00 VII. Cycle 7 A. Operational Characteristics and Procedures, 500 08 02 00 B. Reactor Theory, 450 01 1000 C. Technical Specifications D. Procedure Revisions Review ,
E. Recent Operating Experience Document Review
- 1. LER's
- 2. SOER's 3.5 Revision 0 i Jan 1984 !
COURSE OUTLINE (cont'd)
- 3. Nuclear Network ;
- 4. DCP's
- 5. FSAR Changes
- l l F. Simulator Operations, 500 09 01 00 VIII. Cycle 8 A. Radiation Worker, 600 05 08 00 B. Respirator Training, 600 05 09 00 C. Task Required Courses
- 1. RERP, 550 08 08 00
- 2. Fire Brigade Member, 600 05 03 00 (odd years)
- 3. Fire Brigade Leader, 600 05 05 00 (even years)
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3.6 Revision 0 Jan, 1984
COURSE OBJECTIVES Cycle 1 Objectives
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- 1. Selected Systems Review o Be able to describe, to a level consistent with the grade of operator license, system operation, technical specifications, normal, abnormal and emergency operating procedures, and system or design changes.
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- 2. Technical Specifications ,
o Be able to discuss any Technical Specifications covered during the cycle. This discussion should inclu*: the Limiting Condition for operations, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour should also be expressed.
- 3. Procedure Revisions Review -
o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
- 4. Recent Operating Experience Document Review l
o Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the previous training cycle.
- 5. Be able to satisfactorily perform selected Simulator Operations.
- 6. EF2 Orientation o Be able to discuss site security, area access control, and responsibilities toward security, safety and Quality Assurance.
Cycle 2 Objectives
- 1. Selected Systems Review o Be able to describe, to a level consistent with the grade of operator license, system operation, technical specifications, normal, abnormal and emergency operating procedures, and system or design changes.
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COURSE OBJECTIVES (cont'd) .
- 2. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition for operation, its bases, its applicability and any actie ts that occur within an hour. A general idea of actions in excess of an hour should also be expressed.
- 3. Procedure Revisions Review o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
- 4. Recent Operating Experience Document Review o Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the previous training cycle.
- 5. Be able to satisfactorily perform selected Simulator Operations.
- 6. Safety Electric Switch 480V (SAFLEX 480) o Be able to discuss in detail the operation of SAFLEX 480 volt switches and associated safety precautions.
Cycle 3 Objectives
- 1. Selected Systems Review o Be able to describe, to a level consistent with the grade of operator license, system operation, technical specifications, normal, abnormal and emergency operating procedures, and system or design changes.
- 2. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition for operation, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour should also be expressed.
- 3. Procedure Revisions Review o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
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COURSE OBJECTIVES (cont'd)
- 4. Recent Operating Experience Document Review l o Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the' previous training cycle.
- 5. Be able to satisf actorily perform selected Simulator Operations.
- 6. Task Required Course Cycle 4 Objectives
- 1. Selected Systems Review o Be able to describe, to a level consistent with the grade of operator license, system operation, technical specifications, normal, abnormal and emergency operating procedures, and system or design changes.
- 2. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition for operation, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour should also be expressed.
- 3. Procedure Revisions Review o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
- 4. Recent Operating Experience Document Review o Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the previous
, training cycle.
- 5. Fuel Handling Review o Be able to thoroughly describe technical specifications, interlocks, and applicable procedures.
- 6. Be able to satisfactorily perform selected Simulator Operations. '
Cycle 5 Objectives
- 1. Selected Systems Review 3.9 Revision 0 Jan, 1984
1 COURSE OBJECTIVES (cont'd) o Be able to describe, to a level consistent with the grade of operator license, system operation, technical specifications, normal, abnormal and emergency operating procedures and system or design changes.
- 2. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition for operation, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour should also be expressed.
- 3. Procedure Revisions Review o Be able to discuss any major procedure changes that have occurred since the p*tevious training cycle.
- 4. Recent Operating Experience Document Review o Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the previous training cycle.
- 5. Operating Characteristics and Procedures (OC&P) o Be able to thoroughly discuss integrated plant operattons, expected transients for various accidents, abnormal and emergency operating procedures.
- 6. Be able to satisfactorily perform selected Simulator Operations.
Cycle 6 Objectives
- 1. Mitigating Core Damage o Be able to discuss the mitigation of accidents involving a degraded core.
- 2. 10CFR19, 20, 50, 55 and 100 o Be able to thoroughly discuss pertinent information contained in applicable chapters of 10CFR. ,
- 3. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition i
l 3.10 Revision 0 Jan, 1984 1
COURSE OBJECTIVES (cont'd)
- for operation, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour shculd also be expressed. '
- 4. Procedure Revisions Review o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
- 5. Recent Operating Experience Document Review u Be able to discuss any applicable LER's, SOER's, Nuclear Network, DCP's, or FSAR changes that have been issued since the previous training cycle.
- 6. Thermal Science Review o Be able to solve simple problems with the aid of tables and formulas in the areas of Thermodynamics, Heat Transfer and Fluid
! Mechanics.
- 7. Be able to satisfactorily perform selected Simulator Operations.
Cycle 7 Objectives
- 1. Operating Characteristics and Procedures (OC&P) o Be able to thoroughly discuss integrated plant operations, expected transients for various accidents, abnormal and emergency operating procedures.
- 2. Reactor Theory o Be able to describe selected principles of Nuclear Power Plant Operations including applicable theory.
- 3. Technical Specifications o Be able to discuss any Technical Specifications covered during the cycle. This discussion should include the Limiting Condition for operation, its bases, its applicability and any actions that occur within an hour. A general idea of actions in excess of an hour should also be expressed. ,
- 4. Procedure Revisions Review '
o Be able to discuss any major procedure changes that have occurred since the previous training cycle.
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1 COURSE OBJECTIVES (cont'd) i 5. Recent Operating Experience Document Review i
o Be able to discuss any applicable LER's, SOER's, Nucle'ar Network, DCP's, or FSAR changed that have been issued since the previous training cycle.
- 6.
- Be able to satisfactorily perform selected Simulator Operations.
Cycle 8 Objectives
- 1. Radiation Worker o Be able to thoroughly discuss radiation fundamentals, contami-
, nation and control, radiation exposure limits, methods of minimizing radiation exposure, personnel dosimetry, personnel monitoring and use of protective clothing.
o Demonstrate ability to correctly; don anti "c's", complete administrative requirements for entry into a controlled area, and removal of anti "c's".
- 2. Respira'.or Training o Be able to thoroughly discuss types of respirators, use of each respirator, restrictions associated with each respirator, and safety precautions.
o Demonstrate ability to correctly don, operate, and remove all respirators.
- 3. Task Required Courses
- a. RERP o Be able to describe, to a level consistent with position responsibility, emergency response, exposure control and Emergency Response Fncilities, should an emergency condition occur.
- b. Fire Brigade Member (odd numbered years) o Be able to discuss individual responsibilities, group responsibilities, types of extinguishing devices, and ,
control and extinguishing methods for any type of. fire.
o Demonstrate ability to use all-portable fire extinguishers and hose streams.
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COURSE OBJECTIVES (cont'd) 1
- c. Fire Brigade Leader (even number years) 1 o Be able to thoroughly discuss strategical concepts, fire ground assessment, and emergency command systems inv'olved
, with fire fighting operations.
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CONDUCT OF COURSE Revision 0 Jan, 1984
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COURSE MATERIAL CHECKLIST s
Instructor Materials Student Materials 4
o Technical Specifications o Technical Specifications
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o Marker Board (whita) o Paper / pencils 1
o Marker Bosed Pens 3
o Examinations / Answer Key 4
l o Critique Sheets i
- o Final Safety Analysis Report o 20.000.00 Series Procedures o 22.000.00 Series Procedures e
o 23.000.00 Series Procedures f o 24.000.00 Series Procedures o 29.000.00 Series Procedures i o Flip Chart 1
o Instructor's Guide
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- o LER's o Simulator o Presentation History Forms 4
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!' 4.1 Revision 0 l Jan, 1984
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SUGGESTED METHODS / STRATEGIES During the classroom phase, an instructional / seminar approach is used. The students review aspects of theory and plant operation not normally utilized on a day-to-day basis. The instructor also guides the students through events, analysis of events, and restoration of the Enrico Fermi plant during Infrequent, Abnormal, and Emergency Conditions. Students partici-pate in the seminar, reviewing and building upon their knowledge of Enrico Fermi plant systems, and Control Room / local instrumentation and controls.
During the Simulator Operations phase the instructor guides students through plant evolutions. The students use the latest revisions of actual plant procedure to perform these evolutions. Controls, instrumentation, alarms, interlocks, etc. , associated with the evolution will be identified and explained if necessary. Activities outside the Control Room which are performed by auxiliary personnel (NPPO, NAPPO, Health Physics, etc.) will be identified, explained, and walked through as time permits.
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1 REFERENCES Fermi 2 Technical Specifications L
- j. EFII Final Safety Analysis Significant Event Reports Title 10 Code of Federal Regulations Division 1 Regulatory Guides General Operating Procedures i
Abnormal Operating Procedures T
Emergency Operating Procedures Administrative Procedures System Operating Procedures System Surveillance Procedures NUREG 0737 a
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CENERAL CUIDELINES Ceneral guidelines are established to ensure training standards are met properly. These guidelines are designed to give direction to the Administrator in implementing the course for the NRC Licensed Operators.
The general guidelines are not absolute policy and may be modified as requirements, experience, or conditions dictate.
Pre-Course Preparation The Administrator must observe the following:
- 1. That the course is scheduled without major conflicts.
- 2. That the instructor is notified when the course is to be taught (2 week lead-time).
- 3. That the classroom or training area is scheduled for this course.
- 4. That the instructor has the required material necessary to teach the course.
- 5. That the classroom equipment and materials are ready for use on location.
- 6. That the trainees are notified concerning course schedule, time, and place in written form (2 week lead-time).
- 7. That all necessary administrative and clerical work is completed prior to course implementation.
Course Implementation The Administrator must observe the following:
- 1. Maintain close coordination with instructor to ensure smooth flow of schedule and material.
- 2. Coordinate any request from the instructor for materials not normally used in class.
The Instructor is reopunsible for the following:
- 1. Conduct of trainees
- 2. Following lesson plans
- 3. Safety 4.4 Revision 0 Jan, 1984
4 Testing and Evaluation
- 5. Maintaining starting and finishing time
- 6. Monitoring all tests
- 7. Security of equipment
- 8. Document required records i
Post Course Responsibilities The Administrator should observe the following:
- 1. Record trainee attendance of course (mair tain documentation).
- 2. Record courses completion documentation (grades scores).
- 3. Dictate and record any remedial assignments required (as found appropriatc) in this course.
- 4. Maintain updated progress review of trainee attending this course.
- 5. Review course critiques with instructor.
, 6. Complete all required docunentation, as per Nuclear Operations Training Records procedure.
- 7. Filing of examination in individual's training folder.
- 8. Filing of examination with answers in master training records examination files.
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I 4.5 Revision 0 I
- Jan, 1984
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. l SUGGESTED SCHEDULE Cycle 1
- 1. Selected Systems Review
- 2. Technical Specifications
- 3. Procedure Review Revisions
- 4. Recent Operating Experience Document Review
- 5. Simulator Operations
- 6. Cycle Examination
- 7. EF2 Orientation '
! 4.6 Revision 0 Jan, 1984
e Cycle 1 Mon 7:30 - 8:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 RilR 11:30 - 12:00 Lunch 12:00 - 1:00 RHR 1:00 - 2:00 IIPCI 2:00 - 3:00 RPCI 3:00 - 4:00 Study Period Tues 7:30 - 8:30 RCIC 8:30 - 9:30 RCIC 9:30 - 10:30 ADS 10:30 - 11:30 SLC 11:30 - 12:00 Lunch 12:00 - 1:00 Core Spray 1:00 - 2:00 Core Spray 2:00 - 3:00 Reactor Theory Review Problem 3:00 - 4:00 Study Period Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Fri 7:30 - 11:30 Cycle Examination 11:30 - 12:00 Lunch 12:00 - 2:00 -EF2 Orientation 2:00 - 4:00 EF2 Orientation i
l 4.7 Revision 0 l Jan, 1984 i
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-4.- A+ .-Jv4 m6 41
- s -. .B,. 2--.ja 4h 4m&-l--..a r- ~das. L+dge,.uam.3.J_. -e
+ .b1 3..a--u_.L2 , _ _ -
.--4.5 _hv+4 _ .-m- .a ae%v - -J4 4 4
i i Cycle 2 ,
- 1. Selected Systems Review 4
- 2. Technical Specifications
- 3. Procedure Revisions Review i
- 4. Recent Operating Experience Document Review '
r j 5. Simulator Operations
- 6. Cycle Examination
- 7. Safety Electric Switch 480V (SAFLEX 480) i i
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f 4.8; Revision 0 ,
Jan, 1984
- - . . _ _ ~ _ _ _ _ - _ _ - ._-- - - - _ _ . _ _ - _ . - . . .
l
) Cycle 2 Mon 7:30 - 8:30 Technical Specifications
, 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience l Document Review 10:30 - 11:30 Reactor Pressure Vessel and Internals 11:30 - 12:00 Lunch
- 12
- 00 - 1:00 Reactor Pressure Vessel Instrumentation l 1:00 - 2:00 RBCCW/EECW l 2:00 - 3:00 RSCCW/EECW 3:00 - 4:00 Study Period Tues 7:30 - 8:30 Primary Control and Isolation Control l 8:30 - 9:30 Primary Control and Isolation Control 9:30 - 10:30 Neutron Monitoring (SRM, IRn, PRM, TIP) 10:30 - 11:30 Neutron Monitoring (SRM, IRM, PRM, TIP) 4 11:30 - 12:00 Lunch 12:00 - 1:00 CRDM and CRD Hydraulics 1:00 - 2:00 CRDM and CRD Hydraulics 2:00 - 3:00 CRDM and CRD Hydraulics 3:00 - 4:00 Study Period l
l l Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11:30 Simulator Operations i 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Fri 7:30 - 11:30 Cycle Examination 11:30 - 12:00 Lunch 12:00 - 1:00 SAFLEX (480) 1:00 - 4:00 Simulator Operations 4.9 Revision 0 Jan, 1984
Cycle 3
- 1. Selected Systems Review
- 2. Technical Specifications
- 3. Procedure Revisions Review
- 4. Recent Operating Experience Document Review
- 5. Simulator Operations
- 6. Cycle Examination
- 7. Task Required Course
- 1. Damage and Rescue i
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4.10 Revision - 0 l Jan,-1984. .i j
- 1 J
Cycle 3 Mon 7:30 - 8:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 RWCU 11:30 - 12:00 Lunch 12:00 - 1:00 RBM 1:00 - 2:00 RSCS 2:00 - 3:00 RMCS 3:00 - 4:00 Study Period Tues 7:30 - 8:30 RWM 8:30 - 9:30 Recirc. System and Flow Control 9:30 - 10:30 Recirc. System and Flow Control 10:30 - 11:30 SBGTS 11:30 - 12:00 Lunch 12:00 - 1:00 Control Center HVAC 1:00 - 2:00 Control Center HVAC 2:00 - 3:00 Reactor Theory Review Problem 3:00 - 4:00 Study Period Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11;30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Fri 7:30 - 11:30 Cycle Examination 11:30 - 12:00 Lunch 12:00 - 4:00 Damage and Rescue 4.11 Revision 0 Jan, 1984
Cycle 4
- 1. Selected Systems Review
- 2. Technical Specifications
- 3. Procedure Revisions Review
- 4. Recent Operating Experience Document Review
- 5. Fuel llandling Review
- 6. Simulator Operations
- 7. Cycle Examination 4.12 Revision 0 Jan, 1984 i
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Cycle 4 l
Mon 7:30 - e:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 Diesel Generators 11:30 - 12:00 Lunch '
4 12:00 - 1:00 Diesel Generators 1:00 - 2:00 Main Steam
- 2
- 00 - 3:00 Of f Cas i i 3:00 - 4:00 Study Period I.
- Tues 7:30 - 8:30 Main Turbine Control
! 8:30 - 9:30 Main Turbine Control I 9:30 - 10:30 Main Generator l 10:30 - 11:30 Main Generator j 11:30 - 12:00 Lunch
- 12:00 - 1:00 Feed and Condensate l 1:00 - 2:00 Feed and Condensate 2:00 - 3:00 Remote Shutdown i 3:00 - 4:00 Study Period 4
, Wed 7:30 - 11:30 Fuel Handling Review 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations i
l Thur 7:30 - 11:30 Simulator Operations
- 11:30 - 12:00 Lunch
- 12:00 - 4:00 Simulator Operations I
Fri 7:30 - 11:30 Cycle Examination j 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operattorm 4
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1 4.13 Revision 0 Jan, 1984
Cycle 5
- 1. Selected Systems Review
- 2. Operational Characteristics and Procedures
- 3. Technical Specifications
- 4. Procedure Revisions Review
- 5. Recent Operating Experience Document Review
- 6. Simulator Operations
- 7. Cycle Examination 4.14 Revision 0 Jan, 1984
Cycle 5 Mon 7:30 - 8:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 Electrical Distribution 11:30 - 12:00 Lunch 12:00 - 1:00 Electrical Distribution 1:00 - 2:00 Fire Protection 2:00 - 3:00 Fire Protection 3:00 - 4:00 Reactor Theory Review Problem Tues 7:30 - 8:30 RPS 8:30 - 9:30 RPS 9:30 - 10:30 PRMS and ARMS 10:30 - 11:30 PRMS and ARMS 11:30 - 12:00 Lunch 12:00 - 1:00 Containment Gas Control (Inerting, Venting and Purging) 1:00 - 2:00 OC&P 2:00 - 3:00 OC&P 3:00 - 4:00 Study Period Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Fri 7:30 - 11:30 Cycle Examination 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations 4.15 Revision 0 Jan, 1984
Cycic 6
- 1. Mitigat ing Core Damage
- 2. 10CFR19, 20, 50, 55 and 100
- 3. Thermal Science Review
- 4. Technical Specifications
- 5. Procedure Revisions Review
- 6. Recent Operating Experience Document Review
- 7. Simulator Operations
- 8. Cycle Examination s
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4.16 Revision 0 Jan, 1984 s -
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Cycle 6 s
Mon 7:30 - 8:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 Mitigating Core Damage 11:30 - 12:00 Lunch 12:00 - 1:00 Mitiga;1ng Core Damage 1:00 - 2:00 Mitigating Core Damage 2:00 - 3:00 CFR19, 20, 50, 55 and 100 3:00 - 4:00 CFR19, 20, 50, 55 and 100 Tues 7:30 - 8:30 Thermal Science Review 8:30 - 9:30 Thermal Science Review 9:30 - 10:30 Thermal Science Review 10:30 - 11:30 Thermal Science Review 11:30 - 12:00 Lunch 12:00 - 1:00 Thermal Science Review 1:00 - 2:00 Thermal Science Review 2:00 - 3:00 Thermal Science Review 3:00 - 4:00 Study Period Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Fri 7:30 - 11:30 Cycle Examination 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations l
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~4.17 Revision 0-Jan, 1984
__.__.___--__m__m_.--.___-.a_____________ __ _ _ _ _ _ _ _ _ . _______w
Cycle 7
- 1. Operating Characteristics and Procedures
- 2. Reactor Theory
- 3. Technical Specifications
- 4. Procedure Revistor.o Review
- 5. Recent Operating EAperience Document Review
- 6. Simulator Operations
- 7. Annual Eramination c
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Cycle 7 4
a Mon 7:30 - 8:30 Technical Specifications 8:30 - 10:30 Procedure Revisions Review, Recent Operating Experience Document Review 10:30 - 11:30 OC&P 11:30 - 12:00 Lunch 1 12:00 - 1:00 OC&P 1:00 - 2:00 OC&P ,
2:00 - 3:00 OC&P 3:00 - 4:00 Study Period Tues 7:30 - 8:30 Reactor Theory
. 8:30 - 9:30 Reactor Theory 1
9:30 - 10:30 Reactor Theory 10:30 - 11:30 Reactor Theory 4
11:30 - 12:00 Lunch 12:00 - 1:00 Program Study
, 1:00 - 2:00 Program Study 2:00 - 3:00 Program Study 3:00 - 4:00 Program Study Wed 7:30 - 11:30 Simulator Operations 11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations Thur 7:30 - 11:30 Simulator Operations a
11:30 - 12:00 Lunch 12:00 - 4:00 Simulator Operations I
a Fri 7:30 - 2:30 Annual Examination t
2:30 - 4:00 Simulator Operations 4
4.19 Revision 0 i Jan, 1984
- , v ,E -
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l Cycle 8
- 1. Radiation Worker
- 2. Respirator Training
- 3. Task Required Courses
- a. RERP
- b. Fire Brigade Member (even numbered years)
- c. Fire Brigade Leader (odd numbered years) i 1
l 4.20 Revision 0 Jan, 1984
i Cycle 8 Men 7:30 - 11:30 Radiation Worker (*)
11:30 - 12:00 Lunch 12:00 - 4:00 Respirator Training (*)
Tues 7:30 - 11:30 RERP 11:30 - 12:00 Lunch 12:00 - 4:00 RERP Wed 7:30 - 11:30 Fire Brigade Member (**)
Fire Brigade Leader (***)
11:30 - 12:00 Lunch 12:00 - 4:00 Fire Brigade !! caber (**)
Fire Brigade Leader (***)
Thur 7:30 - 11:30 Fire Brigade Member (**)
11:30 - 12:00 Lunch 12:00 - 4:00 Fire Brigade tiember (**)
Fri 7:30 - 11:30 ' Fire Brigade tiember (**)
11:30 - 12:00 Lunch 12:00 - 4:00 Fire Brigade Member (**)
l
- Time designated is for pre-testing and to upgrade on two (2) unsatis-factory units. Time for other unsatisfactory units will require the individual to put in additional hours as need on Saturday during odd numbered years.
- Course given on even numbered years (1984,1986, etc.)
- Course given'on odd numbered years (1983,1985, etc.)
4.21 Revision O.
Jan, 1984 l
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