ML19327A494
| ML19327A494 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/30/1980 |
| From: | Yundt C PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19327A492 | List: |
| References | |
| TAC-12398, TP-2-2, NUDOCS 8008060262 | |
| Download: ML19327A494 (9) | |
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?ORTLAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR PLANT Revision 8 TRAINING PROCEDURE TP 2-2 LICENSEE RETRAINING PROGRAM APPROVED BY h
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1.0 DESCRIPTION
The purpose of this program is to ensure that all licensed individuals maintain their proficiency and knowledga in all chases of plant oper-ation and related technical areas.
The scope consists of a combination of classroom instructions, on-the-jcb training, periodic orals and operating drills. Cn-the-job training includes practical operating experience in reactivity manipulations, simulator experience, and per-icdic qui =:es covering material assigned for self-study. The participants in the program will be given an annual written examination as well as monthly qui :es in order to evaluate their progress.
All personnel holding Reactor Cperator or Senior Reactor Operator Licenses shall participate in this program. Each individual shall begin the program within 3 months from the date his license is issued.
Newly licensed personnel who have received a license within 3 months of the annual written examination will not be required to participate in that examination.
All lectures covering systems, integrated responses and transients will be taught by instructors possessing a current Senior Operator License.
The term " appropriate sim: lator" as used in this document describes a simulator, approved by the NRC, which reproduces the general operating characteristics of the Trejan Nuclear Plant, and the arrangement of the instrumentation and controls of the simulator is similar to that of the Trojan Nuclear Plant.
The General Manager may make changes to the training program to the extent that the changes do not decrease the scope, time allotted for the program, or frequency in conducting tha different parts of the program. Changes reducing the scope, frequency, and time shall be made pursuant to 10 CFR 50.54.
2.0 CATEGORY I LECTURES 2.1 The Category I Lecture series enccmpasses those areas on which all licensees must receive instruction each year regardless of performance TP-2-2 Page 1 of 9 Revision 8 8 008060 26951
en the annual written examination.
2.2 Category I Lecture series attendance is required of all licensed reactor operators and senior reactor operators.
2.3 Attendance is recorded and absences shall be made up by reviewing the lecture material and discussions with on-shift supervisory personnel or the technical staff. A letter shall be prepared by the absentee's supervisor and forwarded to the Training Supervisor stating that a satisfactory review has been ecmpleted. No more than 20 percent of the required lecture hours shall be completed
'in this manner.
2.4 Category I. Lectures shall consist of a minimt=t of 20 classroom hours per year. All tepics are covered each year, but the scope of each session is determined by the Training Supervisor. Copies of applicable lessen plans and other documents are supplied to all licensees.
2.5 The following topics shall be covered each year during the Category I Lecture series:
2.5.1 Radiation Control and Safety.
2.5.2 Important Plant Design Changes and Mcdifications.
2.5.3 Operating History and Problems.
2.5.4 Technical Specifications.
2.5.5 Major Operational Evolutions.
2.5.6 Important Procedure Changes.
2.5.7 Important Plant License Changes.
2.5.8 Safety-Related Emergency and Off-Normal Instructions.
2.5.9 Mitigation of accidents involving a degraded core.
3.0 CATEGORY II LECTURES 3.1 The Category II Lecture series enccmpasses those areas which are essentially static in nature. These areas include the following topics:
3.1.1 Theory and Principles of Operation.
3.' l. 2 General.amd Specific Plant Operating Characteristics.
3.1.3 Plant Instrumentation and Control Systems.
3.1.4 Plant Protection Systems.
3.1.5 Applicable ' Portions of Title 10, Chapter 1, " Code of Federal Regulations".
3.1.6 Engineered Safety Systems.
3.1.7 Heat Transfer, Fluid Flow and Thermodynamics.
3.2-Individual licensee attendance at category II Lectures is determined TP-2-2 Page 2 of 9 Revision 8 2
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by parformance on the annual written examination. Attendance the following year is required in those subjects where a grade of less than 80 percent is. received.
3.3 Attendance is recorded and absence shall be made up utili=ing in-dividual tutoring by knowledgeable personnel recommended by the -
absentee's superviser. "The absentees are required to pass a written examination ' covering the material presented during the missed lacture.
3.4 The Category II Lecture series is presented on an as-needed basis.
The scope of each series is determined by the Training Supervisor.
Copies of applicable lesson plans and other documents are supplied to all participants. Periodic evaluation quizzes covering the con-tent of the Category II Lecture series be administered by the Training Department.
If a grade of less than 80 percent is received, self-study and tutorial sessions will be assigned by the individual's supervisor. Another written quiz will be administered. This quis may be supplemented by oral examination if deemed appropriate by the individual's supervisor.. The content of ;he quizzes is the same for all licensees and will reflect the tcpi: areas presented during the lecture series.
3.5 The lecture series may be supplemented ay the use of other training techniques including films, videotapes, and other effective training aids.. However, the retraining program will not be based solely upon these other training techniques.
4.0 CN-THE-JOB-TRAINING 4.1 Each licensee shall perform or participate in a ecmbination of react-ivity control manipulations based on the availability of plant equipment and systers. Those control manipulations which are not performed at the plant may be performed on an appropriate simulator.
The use of the Techni:al Specifications should be maximized during the simulator control manipulations. Personnel with senior licenses are credited with these activities if they direct or evaluate control man-ipulations as they are performed. The starred items shall be performed annually and the other items performed on a two year cycle.
- 4.1.1 Plant or reactor startups to include a range that reactivity feedback frem nuclear heat addition is noticeable and heatup rate is established.
4.1.2 Plant Shutdown.
- 4.1.3 Manual control of steam generators and/or 'feedwater during startup and shutdown.
L4.1.4 Boration and or dilution during pcwer operation.
- 4.1.5 Any significant ( > 10%) power changes in manual rod centrol.
4.1.6 Any reactor power change of 10% or greater where load change is performed with' load limit control 4.1.7 Loss of coolant including:
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4.1.7.1 significant PWR steam generator leaks.
4~.1.7.2 inside and outside primary containment.
4.1. 7. 3 ' large and small, including leak-rate determination.
1 4.1.7.4 saturated Reactor Coolant response. ___ ____f 4.1.8 Loss of instrument air (if simulated plant specific).
4.1.9 Loss of electlical power (and/or degraded power sources)
- 4.1.10 Loss of core coolant flow / natural circulation.
4.1.11 Loss of condenser vacuum.
4.1.12 Los s o f s ervice wate r _ _. __ __ _ _
4.1.13 Loss of shutdown ecoling.
4.1.14 Loss of ccmponent cooling system or cooling to an individual component.
4.1.15 Loss of normal feedwater or normal feedwater system failure.
- 4.1.16 Loss of all feedwater (normal and emergency).
4.1.17 Loss of protective system channel.
4.1.18 Mispositioned control rod or rods (or rod drops).
4.1.19 Inability to drive control rods.
4.1.20 Conditions requiring use of emergency baration or standby liquid control system.
4.1.21 Fuel cladding failure or high activity in reactor coolant or off-gas.
4.1.22 Turbine or generator trip.
4.1.23 Malfunction of automatic control system (s) which affect reactivity.
-4.1.24 Malfunction of reactor coolant pressure / volume centrol system.
.4.1.25 P4 actor trip.
4'l.26 Main steam line break (inside or outside containment).
4.1.27 Nuclear instrumentation failure (s).
- 4. 2 ' Each: licensee shall be assigned to the controls of an appropriate
' simulator annually.
Simulator scheduling shall be done by the Training Department.
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s 4.3~ Licensees review applicable documented plant design, license and pro-
,cedure changes.
4. <4 Each licensed reactor operator or senior reactor operator reviews the contents of all abnormal and emergency procedures at least once annually.
4.5 At the beginning of each month four sets of questions are issued tua all licensees.
4.5.1 Each set contains approximately ten questions covering selected
'es from the following list:
4 4.5.1.1 Operating Instructions, including Abnormal and E=cr-gency Operating Instructions.
4.5.1.2 Administrative Orders.
4.5.1.3 Plant Safety Procedures.
4.5.1.4 Operational Quality Assurance Pertaining to Cperations.
4.5 1.5 Radiaticn Protection Manual.
4.5.
3 Reportable Occurrences.
4.5.1.7 Operating Experiences, Reactor Safety and other NRC Publications.
4.5.1.8 Plant Security.
4.5.1.9 Applicable Portions of Title 10 CFRs.
4.5.1.10 Radiological Emergency Response Plan.
4.5.1.11 Theory and Principles of Operation.
4.5.1.12 General.and Specific Plant Operating Characteristics 4.~ 5.1.13 Reactor T'ransients Cur' as.
4.5.2 The questions are answered through self-study and retained by the licensee as study guides.
4.5.3 Near the end of the month, each licensee is administered a written quiz on the month's retraining material.
i 4.5.3.1 The material he is quizzed on is chosen randomly by selection of one of the four sets of questions issued at the beginning of. the month.
4.5.3.2 Any-licensee receiving a monthly quiz grade of less
-than 80 percent is assigned extra study. Upon ec:a-pletion of the extra study, he is again quizzed by random selecticn of one of the three remaining sets of questions. -A grade of less than 80 percent en this quiz will be handled on an individual case basis by the Training Supervisor, i
1 4.5.4 After all licensees have satisfactorily ccmpleted a particular month's quiz, a key to all of the questions is issued by the 9
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,m Training Staff.
4.4.5 If for some reason such as a special school, temporary or pending transfer, hospitalization, etc. an individual is unable to participate in the monthly quiz es, he may be ex-cused for up to 4 months with the written approval of the Training Supervisor.
5.0 PERIODIC 4RALS AND OPERATING DRILLS 5.1 Periodic oral demonstration examinations are administered annually to all licensees. The examinations may be conducted on a continuing basis throughout the year as long as each licensed operator is ex-amined annually.
5.1.1 The Training Supervisor schedules the oral examinations to be administered to the licensees. He also assigns the per-sonnel to conduct the examinations.
5.1.2 The oral examinations are performed by senior licensed personnel using a checklist prepared in advance by the training section that includes the fcllowing areas:
5.1.2.1 Action in the event of emergency conditions.
5.1.2.2 Action in the event of abnormal conditions.
5.1.2.3 Instrument signal interpretation.
5.1.2.4 Response to plant transients.
5.1.2.5 Procedure changes.
5.1.2.6 Plant modifications.
5.1.2.7 Technical specifications.
5.2 Simulated operating drills are conducted periodically for the purpose of evaluating the individual's. operating knowledge and performance ability during simulated abnormal or emergency conditions. The drills are conducted on a shift crew basis and will be evaluated by a senior license holder.
15. 3 Xicensed individuals not normally assigr.ed to the Control Room shall demonstrate satisfactory understanding of the operation of all apparatus and mechanisms, and knowledge of cperating procedures by examining the se areas in the simulated operating drills.
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5.4 The performance of licensed operators involved with actual emergency or abnormal situations may be evaluated in lieu of simulated operating drills.
5.5. Oral examination and operating drill evaluations are assigned a sat-isfactory or unsatisfactory grade.
5.6 Each individual licensee's supervisor is informed by the Training Super-visor of any areas of weakness revealed by the oral examination or the TP-2-2 Page 6 of 9 Revision 8
cperating drills. The Training Supervisor will also recommend an tndividual training program to correct any deficiencies as required.
This individual program will include a reexamination to establish that areas of weakness are corrected.
5.7 An appropriate simulator may be used to meet the cral examination and operating drill requirements. Wherever possible, Trojan operating procedures and Technical Specifications will be utilized when partici-1.ating in a simulator program.
15. 0 EVALUATIONS 6.1 Annually, each supervisor will evaluate all licensed personnel under his supervision. The purpose is to evaluate the performance and competency of individuals based on the supervisor's observations of the individual's day-to-day work. The evaluations will be reviewed by the Operations Supervisor, and a report of the evaluations will be
.nade to the Manager, Cperations and Maintenance. The report will make appropriate reccmmendations such as:
-6.1.1 Recommend continued licensed activiv.es.
6.1.2 Recommend special training in designated areas.
6.1.3 Recommend supervision of licensed activities until the following training is completed.
6.2 Annual written examinations are given to all licensees to determine areas in which retraining may be required. These examinations follow NRC examination format in so far as possible. As a minimum, site administered retraining Reactor Operator and Senior Reactor Operator examinations will contain all sections found on applicable NRC exam-inations. The examination will be prepared in advance and an approved key will be prepared before any examinations are graded.
A grade of less than 80% overall or a section grade of less than 70%, or an unsatisfactory oral examination shall require participation in the Accelerated Training Program as outlined in Section 8.0 of this procedure.
6.3 ' The annual written examination and the monthly quizzes are prepared or approved and administered by the Training Staff and graded by a member of the plant technical, operating, or Training Staff. The Training Supervisor ~ approves all examinations and reviews the annual written exenina* ions for grading techniques and consistency.
7.0 RECORDS 7.1 The following records will be maintained for at least 2 years:
7.1.1 Copies of all examinations and quizzes.
7.1.2 Each licensee's annual examination papers.
7.1.3 Grades fron individual quizzes.
'1 Lecture attendance records.
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7.1.5 Oral examination results.
7.1.6 Records of drill participation.
7.1.7 Records of reactivity control manipulations.
7.1.8
. Annual evaluations.
7.1.9 Monthly quiz questions.
8.0 ACCELEPATED RETPAr1ING PROGPAM 8.1 Jus noted in Section 6.0 a licensee will enter into a full-time accel-ersted retraining program if determined to be deficient in the annual
-written examination or oral examination. The program content will be dictated by the nature of the deficiency. When the licensee is able to satisfactorily pass an equivalent written or oral examination (ad-ministered by an individual designated by the Training Supervisor),
he may resume licensed activities.
8.2 The accelerated retraining programs are developed on an individual basis by the Training-Supervisor and are reviewed and approved by the indiv-idual's supervisor.
8.3 Participation in an accelerated retraining program does not excuse the
-participant from other retraining program activities.
9.C ACTIVE STATUS 9.1 To remain on active status, a reactor operator or senior reactor operator must be permanently assigned to the Trojan Nuclear Plant and actively -engaged in all portiens of the retraining program.
9.2 If a licensee has not.been actively performing the functions of a-reactor operator or senior reactor operator for a period of 4 months
.or longer, he shall, prior to assuming activities pursuant to 10 CFR 55,
-demonstrate his knowledge and understanding of facility operation and administration. -This may be accomplished by reviewing all safety-related emergency and abnormal operating instructions, as well as revisions to the Plant Operating' Manual and any design changes during the period of inactivity. These reviews must be followed by an oral examination given by the Operations Supervisor. 'An unsatisfactory
- esult on the oral examination shall require the operator to have
' additional training in areas where he was weak before taking the exam-ination again.
10.0 -ADMINISTRATION The Training Supervisor will be responsible for maintaining all active records pertaining to this program and will have the overall responsibility for the implementation of the program.
11.0. SCHECULES 11.1 Category I and Category II Lecture schedules are developed baced on TP-2-2 Page 8 of 9 Revision 8 e
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i a 1-year training cycle.
11.2 The annual Category I and Category II training schedules, shoving the; major areas to be. covered, are developed prior to implementation.
The scope of the material to be corered within each area is formu-
. lated and issued to the responsible department well in advance of the date the lecture is to be presented.
12.0 EXEMPTIONS 12.1 The duties of the Training Supervisor and SRO Licensed Specialists who are actively involved in the Retraining Program, exempt them from the annual examinations, monthly quizzes and study guides, oral dem-onstrations, and operating drills in that they are responsible for their preparation, administratien and evaluation.
12.2 Licensed plant administrative and licensed. technical personnel shall palMicipate in this program except to the extent that their normal duties preclude the need for specific retraining in particular areas.
Exemptions from specific areas of the retraining progrma may be granted by the Training Supervisor on an individual basis in accordance with 10 CFR 55 Appendix A.
13.0 REPORTING The Training Supervisor prepares a su::cary of the Retraining Pagram annually.
This summary includes a general report on the Retraining Program and lists existing or potential difficulties with respect to meeting its requirements.
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