ML20132C758
| ML20132C758 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 01/10/1985 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18092A670 | List: |
| References | |
| TP-305, NUDOCS 8507300458 | |
| Download: ML20132C758 (36) | |
Text
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TRAINING PROCEDURE NO. 305 NRC LICENSED OPERATOR REQUALIFICATION PROGRAM FOR SALEM GENERATING STATION
References:
1.
Technical Specifications Section 6.4 2.
INPO's " Guidelines f or Requalification Training and Evaluation", Rev.
O, dated October 8, 1980.
5.
Sections A & C of Enclosure 1 - March 28, 1980 letter to all licensees (Denton letter).
{[
NOTE:
PROGRAM CHANGES program that decre}ade to the approved raqualification training No change may be ases the scope, time allotted for the program, or f requency in. conducting dif ferent parts of the program, unless that change is reviewed and approved by the Manager - Nuclear Training and submitted to the NRC.
Submitted:
/J
[
b-Id 6 Ddte' NuclearTr@YtFgSupervisor-
/
d!N Reviewed:
D'rincipa Trd' i~ng Supervisor -
Dpte/
Salem O rati ns
[
Approved:
/
I tu Date Assishnt Me!r{#ger - Operations Approved:
h
/
[
D 5 te' General Mapa er(/- SalenpOperations
/
Approved:
Manager - Nuclear Training Date Date 11/30/84 840lTP:6 8507300458 850722
{DR ADOCK 05000272 PDR
r e
TABLE OF CONTENTS Page 1.0 Introduction U
1 l.1 Pur pose 1
1.2 Obj ectives 1-13 2.0 Requalification Program 1-5 2.1 Pre-planned Lecture Series 2
2.1.1 Types of Lectures 2
2.1.1.1 Fundamentals Review 2
2.1.1.2 Operational Proficiency 3
2.1.2 Attendance 3
2.1.2.1 Participation 3
2.1.2.2 Records
?
3 2.1.2.3 Absences 3
2,1.2.4 Application of " Bypass Exam" 3
2.1.3 Lecture Presentation 3
2.1.3.1 Approval 3
2.1.3.2 Training Aids 4
2. l'. 4 Study Periods 4
2.1.4.1 Scheduling 4
2.1.4.2 Individual Self-study 4
2.1.4.3 Assignment Sheets 4
l 2.1.5 Evaluation 4
2.1.5.1 Evaluation Quizzes 4
2.1.5.2 Trainee Evaluation 5
f 2.1.6 Exceptions l
5-7 2.2 On-the-job Training 5
2.2.1 Reactivity Manipulations / Plant Evolutions __
l Nuclear Plant Simulator Exercises _
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{
Page 6
2.2.2 Operational Review 6
'2.2.2.1 Modification Review 7
2.2.2.2 Operational Experience Review 7
2.2.2.3 Emergency Instruction Review 7-10 Annual Requalification Examination 2.3 8
2.3.1 Written Examination 8
2.3.1.1 Administration 8
2.3.1.2 Approval 8
2.3.1.3 Review 8
2.3.1.4 Length and Clarity 8
2 3 1.5 Examination Changes 8
273.1.6 Grading _
9 R.' 3.1. 7 Summary 9
2.3.1.8
" Bypass Exam" Option 9
2.3.2 Oral Examination 9
2.3.2.1 Administration 10 2.3.2.2 Topics 10 2.3.2.3 Guidelines 10 2.3.2.4 Summary 10 2.3.3 Newly Licensed Individuals 10-13 2.4 Special Retraining Programs 11 2.4.1 Accelerated Retraining Programs 11 2.4.1.1 Attendance 11 2.4.1.2 Program Content 12 2.4.1.3 Performance S tandards 1
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Page 2.4.2 Inactive Status Retraining 12 12 2.4.2.1 Attendance 12 2.4.2.2 Retraining Content 2.4.2.3 Perf ormance Standards 13 13 2.5 Evaluation 13 2.5.1 Obj ective 13 2.5.2 Inputs 2.5.3 Corrective Action 14 14 2.5.4 Summary 14 3.0 Training Instructor Requalification Program 14 3.1 Document.. Review 3.2 PracticIl Training 14 14 3.2.1 Content 14 3.2.2 In Plant 14 3.2.3 Instructional Skills 15 3.3 Exceptions 15-16 4.0 Records 16 4.1 Program File 16 4.2 Individual File Date 11/30/84 840lTP:6 iii Rev.
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Forms Attendance / Content Documentation TP-305-1 l
TP-305-2 Pre-planned Lecture Series Makeup Documentation Annual Plant Evaluation Documentation TP-305-3 Biennial Plant Evaluation Documentation TP-305-4 Oral Examination Checklist & Documentation TP-305-5 TP-305-6 Watchstanding Documentation Unit 1/2 Emergency Instruction Review TP-305-7 Documentation TP-305-8 Bypass Exam Authorization i
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-1.0 Introduction 1.1 Purpose The Nuclear Regulatory Commission (NRC) requires that all individuals who manipulate the controls of a nuclear facility or supervise the manipulation of those controls, be authorized by a license issued from the Commission.
In addition, the NRC requires that an individual possessing an operating license be enrolled in a continuous and ongoing Requalification Program, to ensure that all licensed individuals maintain a high degree of knowledge and operating ability.
All licensed and certified instructors shall be enrolled in the Requalification Program so they remain cognizant of current operating history, procedural changes, design changes and administrative policies.
1.2 Obj ectives The Licensed Operator Requalification Program objectives are to ensure that all licensed personnel maintain the high levels of skill and knowledge required sfor safe and ef ficient plant operation while meeting iegulatory standards and industry guidelines.
o 2.0 Requalificat,on Program All licensed' operators, except those enrolled in a l
comparable training program, shall participate in the Licensed Operator Requalification Program.
The program outlined below is designed to maintain a licensed individual's knowledge, competence and proficiency, and to meet the requirements imposed by federal regulation for license renewal.
The program will run on an annual basis with all program requirements completed during the two year requalification cycle.
September is considered the starting month for each annual training session.
2.1 Pre-planned Lecture Series A pre-planned lecture series shall be given to all licensed operators on an annual basis.
Scheduled lectures may be deferred due to unanticipated events or conflicts, but should be conducted at a later date.
The lecture series should involve a minimum of 100 contact hours of instruction *, divided among the program topics and appropriately scheduled throughout the requalification annual session.
- A one hour. pe riod in which the course instructor is present or immediately available f or instructing or assisting students.
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r-2.1.1 Types of Lectures 2.1.1.1 Fundamentals Review The Fundamentals Review training session covers areas requiring l
I theoretical knowledges to perform tasks associated with heat transfer, fluid flow, thermodynamics, electricity, mitigation of accidents involving a degraded core and those subject areas delineated in Ref. 1 thru 5.
The emphasis in scope and depth of coverage should be based upon deficiencies identified during examinations or as delineated by station management.
Skills and knowledges identified by the Job Task Analyces should be used to insure that all appropriate areas are covered in a cyclic fashion.
2.1.2.2 Operational Proficiency
.f The Operational Proficiency training sessions cover areas which involve essential plant operational guidelines.
This lecture series shall focus on operational change and experiences (industry wide and at Salem).
Possible topics include the following:
Operating Procedures Technical Specifications Administrative Procedures Significant License Event Reports Related Nuclear Industry Operating j
Experiences 2.1.2 Attendance l
100% participation shall be required of 2.1.2.1 l'
all licensed individuals.*
i
- ATTENDANCE - Exceptions being 1) Those individuals possessing a valid Baccalaureate Degree directly related to the Nuclear lecture topic (e.g., EE, Basic Electricity; ME, Thermo; Engineering, Reactor Theory, etc.)
may be exempt from lectures in those categories, at the discretion of the Principal Training Supervisor, with the exception of lectures addressing operating experience.
- 2) Those training instructors who are actively involved in specific requalification lectures.
- 3) Those l
individuals granted waivers by the Principal Training Supervisor-Salem Operations.
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2.1.2.2 Attendance for-every lecture shall be recorded on Form TP 305-1.
2.1.2.3 Absences.shall be made up within the annual requalification year, via:
1)
Rescheduled lecture attendance or 2)
Self-study and discussion with knowledgeable personnel designated by the Principal Training Supervisor - Salem Operations or his designee:
The absentee may be required to pass a quiz covering l-the material missed.
Self-study / discussion method of lecture makeup should not be used for greater than 20% of the lectures missed (unless permission is given by the Principal Training Supervisor - Salem Operations).
,f Personnel-not completing make-up' work within the required time will be c
treated I.A.W. 10CFR55.31 (C).
2.1.2.4 Persons who have successfully completed the previous year's requalification i
program may be excused from the session if they meet the requirements of Section 2.3.1.8 of this procedure.
2.1.3 Lecture Presentation 2.1.3.1 An approved lesson plan should accompany each training lecture.
The r
lesson plan should be retained as part of the program records.
2.1.3.2 The use of training aids (films, g
slides, models, transparencies, etc.)
is encouraged.
Should films or videotape presentations be used, an instructor shall be available to explain or emphasize the presentation.
2.1.3.3 Instructional objectives should be based on the appropriate JTA (s),
whenever possible.
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2.1.4 Study Periods 2.1.4.1 Study periods should be scheduled in conjunction with the Pre-Planned Lecture Series to provide trainees with an opportunity to reinforce the lecture series and to study new or additional material.
2.1.4.2 Individual self-study should not be substituted for scheduled lectures, except in unusual circumstances, such as instructor unavailability.
2.1.4.3 Study assignment sheets may be used as a method of structured self-study.
Segment exam questions shall not be stated exactly as they appear on the study assignment sheet.
Study assignment sheets should be used to reinforce concepts presented during the lecture series.
2.1.5 Ev,aluation 2.1.5.1 Periodic evaluation quizzes covering the content of the requalification lecture series should be administered.
The quizzes will be used to evaluate the trainee's knowledge, effectiveness of the lecture series and overall' effectiveness of the presentation.
If the quiz requires any reference material, the material shall be provided by the training s'taff.
This information will be identified on the quiz cover sheet and should be limited to steam tables, emergency plan procedures and equation sheets.
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2.1.5.2 The effectiveness of the lecture series j
should be evaluated by the trainees and the Nuclear Training Supervisor.
1)
Trainee evaluation may be in the form of written critiques or oral seminars.
2)
Nuclear Training Supervisor evaluation should be directed toward the effectiveness of the presentation.
3)
The results of these evaluations shall be considered for subsequent requalification training.
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Page 4 of 16 Rev.
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results of this evaluation should be forwarded to the Principal Training Supervisor for review and comment.
2.1.6 Exceptions Any licensed operator enrolled in a senior operator upgrade program shall be credited with successful completion of the annual classroom training portion of the licensed operator requalification program.
2.2 On-the-job Training The purpose of this training is to ensure that each licensed operator maintains an acceptuble level of skills and familiarity associated with plant systems, controls and coperational procedures. On-the-job training is divided into two types of training:
Reactivity Manipulations / Plant Evolutions Operational Review 2.2.1 Reacfivity Manipulations / Plant Evolutions Durfng the two year term of the NRC license, each licensed individual shall participate in a variety of reactivity control manipulatins and plant evolutions.
During each annual cycle, each licensed individual shall participate in the activities listed on attachment TP-305-3. On a two year cycle basis, each licensed individual shall participate in the evolutions listed on attachment TP-305-4.
Note:
Evolutions marked with an asterisk are required, others are recommended.
Reactivity manipulations and plant evolutions may be completed at the station or on a training simulator.
Licensed operators (RO) shall actually manipulate the controls.
Licensed senior operators (SRO) may either manipulate or actively supervise the manipulation of the controls.*
Response to abnormal / emergency conditions should include the use of alternate methods of accomplishing a given function.
Exercises involving multiple failures and/or operator error shall be included.
Utilization of applicable plant procedures, Emergency Plan and Technical Specifications during the training exercise should be maximized.
2.2.1.1 Nuclear Plant Simulator Exercises a)
Licensed individuals shall I
participate in a structured training program, involving at 840lTP: 6 Date 11/30/84 Page 5 of 16 Rev.
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least twenty (20) hours of direct interaction with the simulator nuclear plant control panel, on an annual basis.
b)
During the simulator training sessions, the team concept should be utilized, emphasizing individual roles in reporting, assignment of operational duties, use of plant procedures and use of Technical Specifications.
No more than four (4) licensed individuals should be assigned to participate in a simulator training session requiring direct interaction with the control panel, c)
Simulator training schedules will be coordinated with simulator group and conducted I.A.W.
simulator procedures.
2.2.2 Operational Review JOperational review provides a mechanism for the
- ontinuing updating of on-shif t personnel, including the dissemination of new or changing information.
2.2.2.1 Modification Review a)
A continuing system (Ope ra tions Department Information Directives (ID)) has been established to ensure licensed individuals are aware of plant design changes, equipment modifications, proced ural changes and Technical Specification changes.
The Rising Sun -
Operations Daily Newsletter is also used to provide Unit status, DCR update reports and miscellaneous j
notices to all operations l
personnel.
Completed ID routing sign-off sheets shall be forwarded to the Training Center Librarian and retained as documentation of review completion, b)
The Principal Training Supervisor or his designee shall review the Operations Daily Newsletter, LERs, etc., and ID's and forward those items requiring expanded coverage to the Training Supervisor -
Licensed Operator Regualification.
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2.2.2.2 Operating Experience Review a)
A continuing system (Ope ra tions daily newsletter and ID's) has been established to ensure licensed individuals review operating experience f rom the station and applicable segments of the nuclear indus try.
Operating experience should be obtained f rom, but not limited to, the following:
license event reports (LERs), NSAC/INPO significant event reports and nuclear industry publications /pe riodicals.
Completed routing sign-off sheets shall be forwarded to the Training Center Librarian and retained as documentation of review completion.
b)
The Principal Training Supervisor or his designee shall review operating experience items and a'
forward those requiring expanded coverage to the Nuclear Training Supervisor - Licensed Operator i
Requal.
Selected nuclear plant accidents / transients should be analyzed and integrated into the nuclear plant simulator exercises as appropriate.
I 2.2.2.3 Emergency Instruction / Emergency Operating Procedure Review All Emergency Instructions / Emergency l
Operating Procedures shall be reviewed by all licensed personnel on an Annual basis.
Completed check-of f sheets (TP-305-7) shall be forwarded to the Training ' Supervisor - Licensed Operator Requalification, who will ensure compliance and retain completed sheets as documentation of review completion.
2.3 Annual Requalification Examination Each licensed operator shall be given four segment l
requalification examinations to determine the following:
areas in which retraining is needed, knowledge of the topics covered in the Requalification Program and knowledge of abnormal and emergency procedures.
The annual examination shall consist of four segmented written exams and a comprehensive oral l
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f exam.
Personnel not achieving the established minimum acceptable performance level, shall be enrolled in an Accelerated Retraining Program.
A recommendation concerning the continuation of licensed duties shall be made by the Manager -Nuclear Training to the Assistant General Manager -Salem Operations.
2.3.1 Written Examination 2.3.1.1. A written examination shall be 4
administered at the completion of each training segment.
Examinations should reflect only those areas addressed during the previous training segmeng.
The combination of all segment exams will constitute the annual written examination.
2.3.1.2 The examination and answer key shall be reviewed and approved by the Principal Training Supervisor or his designee prior to use.
213.1.3 The examination and answer key should
~
be reviewed by the Principal Training Supervisor - Program and Professional i
i Development, or his designee, prior to, use.
2.3.1.4 The examination should be administered to a member of the training staff (for determination of exam length and clarity) prior to use.
2.3.1.5 To prevent compromise, at least 33% of the examination shall be changed each time it is administered.
The examination shall be administered in accordance with NRC requirements (i.e.,
dedicated restroom facility, desk spacing, exam proctor, etc.).
2.3.1.6 The written segment examination shall be administered and graded by a member of:
the station technical staff, station management staff, training l
department, independent consulting firm l-or the NRC.
A grade ot 70%
m each exam and an overall grade of 80% is required for satisfactory performance.
If an individual fails to obtain a grade of 70% or greater, his exam shall
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be reviewed by a dif ferent person. If the review results in concurrence between the first and second review, then the exam failure shall stand. If there is disagreement between the first and second reviewer, a third independent review shall be conducted with a majority ruling.
2.3.1.7 A summary of the written examination results shall be furnished to the Assistant General Manager - Salem Ops.
by the Manage r - Nuclear Training within 15 working days.
2.3.1.8 Any licensed operator who has successf ully completed the previous year's Requalification Annual Segment Exams with no sectiond 80% and an overall average of t 90% may choose to take any segment exam prior to the lecture series (referred to as the
" Bypass Exam").
These candidates f
must be approved by the Principal Training Supervisor - Salem Operations.,
i The. Training Supervisor - L.O. Requal should fill out form TP-305-8 and forward it to the appropriate individuals.
The student shaft be excused f rom that segment's lecture series and exam by attainingl 80% on the bypass exam.
The student will be' allowed one opportunity per segment to successf ully l
complete the bypass exam.
2.3.2 Oral Examination 2.3.2.1 Oral Examination shall be administered to each licensed operator.
The examinations shall be conducted by l
l personnel holding an equivalent o pe ra tor license or certification on the Salem Plant, or a plant of similar d'esign, or by personnel who have successf ully completed education and training programs required for such a license or certification.
The examination should consist of an in-plant walk-thru and may include a test on the Salem Simulator.
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2.3.2.2 The Oral Examination should focus on those areas important to the safe operation and shutdown of the reactor and the prevention of the release of fission products to the environment.
2.3.2.3 Examinations shall be conducted under a structure which ensures consistency in questioning and evaluation.
The following guidelines should be considered:
1)
The use of an oral examination summary sheet (TP-30 5-5 ) or the equivalent simulator performance measurement tool.
2)
The overall evaluation should be made on a pass / fail basis.
3)
Comments en individual strengths
./
and weaknesses should be documented and discussed with the individual at the completion of the i
examination.
2.3.2.4 A summary of the Oral Examination results shall be furnished to the Assistant General Manager -Salem Ops, by the Manager -Nuclear Training within 15 working days.
2.3.3 Newly Licensed ~ Individuals Upon receipt of their license, individuals shall enter the Requalification Program by attending subsequent requalification sessions with their assigned shift.
2.3.3.1 If an individual has received a license within the six month period prior to to his shift taking the Oral Examination, this individual may be granted exemption oral.*
2.3.3.2 If an individual has received a license during his shift training segment, this individual may be granted exemption from taking that segment exam.
2.4 Special Retraining Programs Specific retraining programs for licensed individuals may be required to upgrade or refresh knowledge and skills related to licensed duties.
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2.4.1 Accelerated Retraining Program This program is for licensed individuals exhibiting deficiencies and/or failing to meet the minimum grade requirements on the written segment or oral examinations.
2.4.1.1. Preliminary Action (s) l The Principal Training Supervisor shall notify the Manager - Nuclear Training of any licensed operator required to participate in an Accelerated Retraining Program.
The Manager -
Nuclear Training shall make a recommendation to the Assistant General Manager - Salem Operations as to whether the licensed operator should, in addition, be relieved from all or a portion of his licensed duties until successfully retested.
In making this recommendation, the Manage r -Nuclear Training should consider, but not be
/
limited to:
1)
The requalification exam rspults
}
2)
Overall performance in the current program.
3)
Past perf ormance in the program.
[
4)
Licensed duty performance record He shall confer with the Operations Manager - Salem to establish this.
5)
Performance on the simulator.
6)
Extenuating circumstances which may have influenced the results on a specific requal examination.
l 2.4.1.2 Program Content The Accelerated Retraining Program should be specifically structured to upgrade knowledge and skills identified as deficient.
Examination categories and areas which performance standards were not met shall be covered in the i
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program.
The Principal Training Supervisor - Salem Operations shall approve the Accelerated Retraining Program.
2.4.1.3 Perf ormance S tandards 1)
Successful completion of the Accelerated Retraining Program shall be determined by administering an examination.
The examination shall cover all areas of the segment written and/or otal examination originally failed.
The examination shall be conducted by individuals designated by the Principal Training Supervisor in accordance with Section 2.3.2.1.
2)
Satisf actory perf ormance in the Accelerated Retraining Program shall be a score of at least 80% on the written examination and/or a
,f pcssing evaluation on the oral examination.
)
3)
In the event that these performance standards are not met by the s
individual, the Assistant General Mgnager - Salem Operations (based on recommendations by the Manager -
Nuclear Training) shall determine whether the individual should be permanently removed f rom licensed duties or if additional upgrading efforts are. appropriate.
2.4.2 Inactive S tatus Retraining 2.4.2.1 Active status is maintained by the satisf actory performance of licensed duties and participation in the Licensed Requalification Program.
If an individual has not actively carried out licensed duties for a period in excess of four months, a special retraining program and/or evaluation L
shall be completed prior to resuming licensed duties (10 CFR5 5. 31 (e)).
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2.4.2.2 In the event that a licensed individual l
does not maintain an active status, the Manager - Nuclear Training shall i
determine specific requirements that i
must be met prior to resuming licensed duties.
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2.4.2.3 The specific reqairements established shall include the administering of an oral and/or written exam similar in scope and format to the requalification exams.
The same performance standards apply to these exams.
NOTE:
ALL NON-SHIFT LICENSED PERSONNEL, EXCEPT (DUE TO THEIR INTIMATE INVOLVEMENT IN PLANT OPERATIONS) FOR THE GENERAL MANAGER-SALEM OPERATIONS, ASSISTANT GENERAL MANAGER - SALEM OPERATIONS, OPERATIONS MANAGER, THE OPERATING ENGINEER, AND THE SENIOR OPERATIONS SUPERVISOR, WILL ACTIVELY PARTICIPATE IN CONTROL ROOM OPERATION A MINIMUM OF ONE SHIFT EACH CALENDAR QUARTER.
DURING THIS PERIOD, THESE LICENSED PERSONNEL MUST ASSUME THE DUTIES OF THE SHIFT LICENSED OPERATOR OR THE SHIFT SUPERVISOR IN THE CONTROL ROOM AREA.
PARTICIPATION SHALL BE DOCUMENTED BY AN ENTRY IN CONTROL ROOM LOG 1 AND BY COMPLETING FORM TP-305-6 AND FORWARDING TO THE TRAINING CENTER, 2.5 Evaluation 2.5.1 The.Requalification Program should be evaluated at the completion of each annual requalification,
tession to determine the effectiveness of the program in meeting designated requirements and to identify the job performance results attributable to training.
2.5.2 The Principal Training Supervisor or his designee should conduct this evaluation / review.
He should utilize, but not be limited to, the following inputs:
1)
Inspection, audit and evaluation reports of requalification training completed by outside organizations and station personnel.
2)
Program oral and written examination results.
3)
Plant operational problems related to licensed individual knowledge or skill deficiencies.
4)
License Event Reports, related to licensed individual performance, from the station and the nuclea r indus try.
5)
Regulations and standards af fecting licensed operator training.
6)
Trainee course critiques l
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2.5.3 Requalification Program deficiencies and licensed operator retraining needs, determined by the review, shall be identified and ref erred to the Salem Operations Training Review Group
. for further action, as necessary.
2.5.4 A summary of the Annual Examination results shall be forwarded to the Manager - Nuclear Training and the Assistant General Manager -
Salem Operations within 30 days of the Annual Requalification Session completion date.
3.0 Training Instructor Requalification Program 3.1 Document Review All training instructors licensed or certified for Salem shall review pertinent. operating records, procedures, design changes and modifications selected by the Principal Training Supervisor or his designee.
These documents include, but are not limited to, the following:
1)
Emertjency and casualty procedures 2)
Tectnical Specification changes 3)
Operation. department information directives 4)
Significant design changes 5)
NRC I&E bulletins, circulars and information notices.
6)
Significant License Event ~ Reports 3.2 Practical Training 3.2.1 Each training instructor licensed or certified on the Salem Plant shall perform or evaluate the performance of those manipulations identified on attachments TP-305-3 and TP-305-4.
3.2.2 Each licensed or certified training instructor should meet the requirements of the NOTE: that follows 2.4.2.3.
3.2.3 Trai'ning in instructional skills such as classroom presentation and test development should be conducted as necessary. and in accordance with the Instructor Development Manual.
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3.3 Exceptions All licensed training instructors shall participate in The the Licensed Operator Requalification Program.
Principal Training Supervisor - Salem Operations may excuse individual instructors from all or a portion of this program if, by the end of the two year they have received equivalent requalification term, training through the performance of their instructor Instructor duties include such items as:
duties.
Lecture presentations Lesson plan review Written examination / answer key preparation Written examination grading Oral examination administration Simulator, Lesson Preparation Simulato? Lesson Presentation 4.0 Records Auditable records of the Requalification Program and each licensed individual's performance in the RequalificationThe Program shall be maintained for the life of the plant. Nuclea
+
maintaining the program records in accordance with approved procedures.
The following documentation should be maintained in the 4.1 program file.
Composite copy of exatiination results 1)
An as presented copy of the program schedule 2)
Operational review beries participation sign of f 3) sheets Lecture series attendance records 4)
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6 840lTP:6 Page 15 of 16
A copy of all written examinations administered and
.5) associated answer keys.
6)
Lecture series lesson plans The following documentation should be maintained in the 4.2 individual's training file.
Oral and written examinations 1)
A copy of any license application or license 2) renewal A copy of completed reactivity manipulation check 3) of f sheets, and plant evolution check of f sheets, emergency instruction review sheets and watchstanding verification forms.
A copy of simulator training participation records 4)
Any documentation to or f rom the NRC ref erencing 5) the individuals training or qualification.
Any f ternal documentation associated with the 6) individuals adm.ission to, elimination from or stat.s in a training program.
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6 840.1P:6 Page 16 of 16
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TP-305 l
SALEM UNITS 1 & 2 LICENSED OPERATOR REQUALIFICATION PROGRAM ATTENDANCE / CONTENT DOCUMENTATION l
TRAINING DATE:
LOCATION:
Name (Please Print)
Signature Social Security Number i.*
J i
Instructor Hours Subject TOTAL HOURS:
Classroom:
Examinations:
Other:
(Explain)
Study:
Walk Throught Film:
Videotape:
Simulator:
Date 11/30/84 Form TP 305-1 Rev.
6 TP840* 6
TP-305 SALEM UNITS 1 & 2 LICENSED OPERATOR REQUALIFICATION PRE-PLANNED LECTURE SERIES MAKEUP DOCUMENTATION POSITION:
EXAMINEE:
LICENSED:
OPERATOR LICENSE DATE:
SENIOR OPERATOR LICENSE E XAMINER:
POS ITION:
E XAM AREA :
1 EXAM TYPE:
ORAL
}
WRITTEN COMMENTS:
ORAL:
PASS WRITTEN:
(GRADE)
FAIL i
Date 11/30/84 TP8401:6 Form TP 305-2 Rev.
6
SALEM UNITS 1 & 2 LICENSED (PERATER ltESIALIFICATIEM PLANT EVOLIIT1(M5 00Ct K MTATIGN LICDISE: RI)/SRO (Circle)
MIE:
Z 3 S /S /IM5TittETER AlcalAL EVOLUTIONS Performed (Circle)
DATE INITIALS
- Reactor startup to PQAH PLANT /SIM.
Plant 91utdown PLANT / SIN.
- Menual control of S/G Level and/or Fdw. ductng Plant S/U PLANT /SIM.
' Manual control of S/G Level and/or Fdw. durtng Plant S/D PLANT /SIM.
Boratton and/or Dilution during Plant Operation PLANT /SIM.
- 10% Power Change with Control Rods in Manual PLANT /SIM.
10% Power Change with Turbine Controls in Manual PLANT /SIM.
Manuel Turbine Startup PLANT /SIM.
0ecay Heat Removal System Operetton 7
PLANT /SIM.
Reactor Trip PLANT /SIM.
Turbine or Generator Trip
)
PLANT /SIM.
LOCA: S/G Tube Leak Rupture PLANT /SIM.
'LOCA: Inside Contatnment PLANT /SIM.
'LOCA: Cutside Contatnment PLANT /SIM.
Saturated Reactor Coolant Response
'LOCA:
PLANT /SIM.
' Loss of R.C. Flow /Netural Ctreulation PLANT /SIM.
' Loss of all feedwater PLANT /SIM.
Loss of Shutdown Cooling PLANT /SIM.
Incore Monttortng System PLANT /SIM.
Control Room inaccesabtitty PLANT /SIM.
Control Room Calculations PLANT /51H Heat Balance / Reactivity Balance / Inventory Balance durtog actual plant The above ANNUAL EVOLUTIONS shall be performed at a nuclear plant simulat However, to recetve credit for performance of these evoluttons NOTE 3 operations.
t should be performed this form and forwarded to the TRAINING CENTER.The *(astertsk but are not required.
Some required Stenntal evolutiona may be suggested Annual evolutions.they direct or e
- SRG-LICENSED personnel may receive credit for an evolut ton be included annually.
- A t9 al of ten (10)
Date 11/30/04 t
Form IP-305-3 Rev.
6 TP840186
SALON UNITS 1 & 2 LICDISED (FDIATER RORinLIFICATIlm PLANT EVOLUTIONS DOCLSENTATIIBI LICENSE: R0/SRO NAME:
(Ctrele) 2 I 5 /S / INSTRUCT,0R Perforeed BIENNIAL (Every 2 years) EVOLUTIONS (Ca rele)
DATE INITIALS
' Nuclear Instrumentation Failure (s)
PLANT /SIM.
- Loss of Protective System Channel (s)-
PLANT /SIM.
- Misposttioned Control Rod (s) (or rod drops)
PLANT /SIM.
- Insbility to Drive Control Rod (s)
PLANT /SIM.
- Condttsons Requiring Use of the Emergency Boretton System PLANT /SIM.
- Fuel Cindding Feiture, or High Activity in RCS, or High Activity in PLANT /SIM.
Off-Gee
- Melfunctton of Automette Control System (s) which Af fect Reactivity PLANT /SIM.
- Melfunction of Reactor Coolant Pressure / Volume Control System PLANT / SIN.
' ' loss of Instrument Air PLANT /SIM.
- Loss of Electrical Power end/or Degraded Power Source PLANT /SIM.
- Loss of Condenser Vacuum PLANT /S!M.
- Loss of Service Water PLANT /SIM.
- Loss of Component Cooling System or Cooling to en indavadual Component PLANT /SIM.
- Main Steam Line Break (Inside or Outstde Containment)
PLANT /SIM.
- Plant Shutdown PLANT /SIM.
- Boretton and/or dilution durtng power operetton PLANT /SIM.
- 10% Power Change with Turbine Controls in Manual PLANT /SIM.
- Loss of Shutdown Cooling PLANT /SIM.
- Turbine or Generator trip PLANT /SIM.
- Reactor trtp PLANT /SIM
- The above BIENNI AL EVOLUTIDNS shall be performed at a nuclear plant simulator or during actu However, to recetve credit for performance of these evolut tons they must be documented on NOTE:
operations.
this form and forwarded to the IRAINING CENTER.
- The '(estertsk) marked evolut tons shall be performed satisfactorily, other stems should be performe but are not required.
' SkO-LICENSED personnel may recetve credit for an evolution they direct or evaluate as at is p
- bome required Biennial evolut tons may be suggested Annual evolut tons.
Date 11/30/04 Form IP-305-4 IPS401 6 Rev.
6
TP-305 SALEM UNITS 1 & 2 LICENSED OPERATOR ORAL EXAMINATION CHECKLIST AND DOCUMENTATION
~
POS ITION:
EXAMINEE:
LICENSED:
OPERATOR LICENSE DATE:
SENIOR OPERATOR LICENSE EXAM PURPOSE:
ANNUAL ORAL EXAMINATION DEFICIENT ANNUAL WRITTEN - LICENSED EVALUATION f
DEFICIENT ANNUAL ORAL - LICENSED EVALUATION
}
REMEDIAL TRAINING ORAL EXAMINATION INACTIVE STATUS ORAL EXAMINATION OTHER POSITION:
EXAMINER:
DATE:
EXAMINATION AUTHORIZATION:
EXAMINER SIGNATURE:
RECOMMENDATION:
PASS FAIL DATE:
COMMENTS:
1 of 5 Date 11'/30/84 TP8401:6 Form TP 305-5 Rev.
6
TP-305 ORAL EXAMINATION GRADE /
SUMMARY
SHEET Examiner:
lxaminao:
Date:
'OOitiCn:
S U
M Licensed Duties and Responsibilities of Position 1.
(
S U
M Abnormal Conditions 2.
Actions in the Event og S
U M
Actions in the Event of Emergency Conditions 3
11/35/84 Date
~
2 of 5 Rev.
6 Form TP 305-5 TP840126
TP-305 ORAL EXAM GRADE /
SUMMARY
SHEET (Continued)
S U
M Interpretation of Instrumentation Response 4.
S U
M 5.
Plant Transient and Accident Report f
F 1
i S
U M
6.
Plant Modifications i
i 3 of 5 Date 11/30/84 TP840126 Form'TP 305-5 Rev.
6
TP-305 ORAL EXAM GRADE /
SUMMARY
(Continued)
S U
M 7.
Procedures and Procedural Changes S
U M
8.
Technical Specifications S
U M
9.
Emergency Plan 4 of 5 Date 11/30/84 TP8401:6 Form TP 305-5 Rev.
6
i TP-305 ORAL EXAM GRADE /
SUMMARY
(Continued)
S U
M Plant Operating History and Problems 10.
S U
M Related Nuclear Industry Operating Ex pe rience 11.
ja Su-'nry STRENGTHS :
WEAKNESSES :
Oral Exam Summary Reviewed:
Date Examinee Signature Date Examiner S ignature Date 11/30/84__
5 of 5 Form TP 305-5 Rev.
6 TP840136
TP-305 SALEM UNITS 1 & 2 OFF-SHIFT LICENSED OPERATOR WATCH STANDING DOCUMENTATION
~
has I certify that __
(Off-Shif t Licensed Operator) satisf actorily assumed (under instruction) and performed the duties of:
Senior Shif t Supervisor Shi[t Supervisor Nuc lear Control Operator on the 12-8, 8-4, 4-12 shift this date of (Circle One)
SHIFT SUPERVISOR / SENIOR SHIFT SUPERVISOR PLEASE FORWARD THE COMPLETED FORM TO THE TRAINING CENTER.
Date 11/30/84 TP8401:6 Form TP 305-6 Rev.
6
TP-305 0
/
'AME : __
UNIT l/2 EMERGENCY INSTRUCTIONS REVIEW FORM I
INITIALS /DATE
/
E.I.
I-4.0 Saf ety Injection Initiation
/
Flooding and/or High Wind Conditions I-4.1
/
I-4.2 Recovery F, rom Saf ety Injection
/
I-4.3 Reactor Trip
/
I-4.4 Loss of Coolant
/
I-4.5 Loss of RCP and/or Flow
/
I-4.6 Loss of Secondary Coolant f
/
I-4.7 Steam Generator Tube Failure
/
I-4.8 Rod Contre} System Malfunction
/
\\
I-4.9 Blackout
/
I-4.9A Loss of all AC
/
I-4.10 Control Room Evacuation
/
I-4.ll High Re&ctor Coolant Activity
/
I-4.12 Loss of Feedwater
/
I-4.13 Loss of Circulating Water / Loss of Vacuum 1 of 2 Date 11/30/84 Form TP 305-7 Rev.
6 TP8_401:6_
TP-305 1AME:
UNIT l/2 EMERGENCY INSTRUCTIONS REVIEW FORM INITIALS /DATE
/
Service Water System Malfunction E.I.
I-4.14
/
I-4.15 Loss of Component Cooling
/
I-4.16 Radiation Incident (Unit 1)
/
I-4.16A Radiation Incident (Unit 2)
/
I-4.17 Partial Loss of Reactor Coolant
/
I-4.18 Loss of Control Air
/
Malfunction of Nuclear Instrumentation I-4.19
/
I-4.20 Failure of. eactor Coolant Pump
/
I-4.21 Condenser tube Leal
/
I-4.22 Loss of RHF Shutdown Cooling
/
I-4.23 Loss of Containment Integrity
/
Malfunction of Pressurizer Relief /Saf ety Valve I-4.24
/
I-4.25 Fuel Handling Incident
/
I-4.26 Secondary System Leaks Date 11/30/84 2 of 2 Rev.
6 Form TP 305-7 MEll---. __ __ _ __
o TP-305 Name EMERGENCY OPERATING PROCEDURES REVIEW FORM INITIALS /DATE REACTOR TRIP / SAFETY INJECTION SERIES EOP-TRIP-1, Reactor Trip or Saf ety
/
Injection
/
EOP-TRIP-2, Reactor Trip Response
/
EOP-TRIP-3, SI Termination EOP-TRIP-4, Natural Circulation Cooldown
/
EOP-TRIP-5, Natural Circulation Rapid
/
Cooldown without RVLIS EOP-TRIP-6, Natural Circulation Rapid
/
Cooldown with RVLIS LOSS OF COOLANT NCCIDENT SERIES
/
EOP-LOCA-1, Loss of Reactor Coolant EOP-LOCA-2, Post-LOCA Cooldown and
/
Depressurization
/
EOP-LOCA-3, Transf er to Cold Leg Recirculation
/
EOP-LOCA-4,-Transfer to Hot Leg Recirculation
/
EOP-LOCA-5, _ Loss of Emergency
' Recirculation
/
EOP-LOCA-6, LOCA Outside Containment LOSS OF SECONDARY COOLANT SERIES
/
EOP-LOSC-1, Loss of Secondary Coolant EOP-LOSC-2, Multiple SG Depressurization
/
STEAM GENERATOR TUBE RUPTURE SERIES
/
EOP-SGTR-1, S team ' Generator Tube Ruptureg
/
EOP-SGTR-2, Post-SGTR Cooldown EOP-SGTR-3, SGTR with LOCA - Subcooled
/
Recovery EOP-SGTR-4, SGTR with LOCA - Saturated
/
Recovery EOP-SGTR-5, SGTR without PZR Press Control
/
LOSS OF POWER SERIES
/
EOP-LOPA-1, Loss of All AC Power
/
EOP-LOPA-2, Loss of All AC Power Recovery /SI Not Required
/
EOP-LOPA-3, Loss of All AC Power Recovery /SI Required STATUS TREES
/
SOP-CFST-1, Critical Safety Function Status Trees Date 11/30/84 Page 1 of 2 MMNt-7/5t Rev.
TP-305 Name FUNCTION RESTORATIONS INITIALS /DATE EOP-FRSM-1 RESPONSE TO NUCLEAR POWER
/
GENERATION
/
EOP-ERSM-2 RESPONSE TO LOSS OF CORE 3HUTDOWN EOP-FRCC-1 RESPONSE TO INADEQUATE CORE
/
COOLING EOP-FRCC-2 RESPONSE TO DEGRADED CORE
/
COOLING EOP-FRCC-3 RESPONSE TO SATURATED CORE
/
COOLING CONDITIONS EOP-FRHS-1 RESPONSE TO LOSS OF SECONDARY
/
HEAT SINK EOP-FRHS-2 RESPONSE TO STEAM GENERATOR
/
OVLRPRES'URE S
EOP-FRHS-3 RE.1PONSE TO STEAM GENERATOR
/
HI'H LEVEL EOP-FRHS-4 RELPONSE TO LOSS OF SG
/-
ATMOSPHERIC RELIEFS AND CONDENSER DUMP VALVE EOP-FRHS-5 RESPONSE TO SG LOW LEVEL
/
EOP-FRTS-1 RESPONSE TO IMMINENT PRESSURIZED
/
THERMAL SHOCK CONDITIONS EOP-FRTS-2 RESPONSE TO ANTICIPATED PRESSURIZED ~
/
THERMAL SHOCK CONDITIONS EOP-FRCE-1 RESPONSE TO EXCESSIVE CONTAINMENT
/
P RESSURE EOP-FRCE-2 RESPONSE TO HIGH CONTAINMENT
/
SUMP LEVEL EOP-FRCE-3 RESPONSE TO HIGH CONTAINMENT
/
l RADIATION l
EOP-FRCI-l RESPONSE TO HIGH PRESSURIZER
/
LEVEL EOP-FRCI-2 RESPONSE TO LdW RCS INVENTORY
/
EOP-FRCI-3 RESPONSE TO VOID IN REACTOR
/
VESSEL l
I Page 2 of 2 Date 11/30/84 3mm tt
t TP-305
.g BYPASS EXAM AUTHORIZATION The following person has requested permission to take Segment
" Bypass Exam" in order to fulfill the requirements for this requalification session.
Name:
Requirements of TP-305-2.3.1.8 satisfied:
N
..f Training Supervisor - L.O. Requalification
.l Permission Granted:
Operating Engineer - Salem Permission Granted:
Principal Training Supervisor - Salem Operations Exam Completed:
Grade:
Date 03/08/84 TP8401:6 Form TP 305-8 Rev.
6
. - _