ML20140H032
| ML20140H032 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/01/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20140G761 | List:
|
| References | |
| TRPR-33.0, NUDOCS 9705120289 | |
| Download: ML20140H032 (39) | |
Text
o - .e POINT BEACil NUCLEAR PLANT TRAINING PROGRAM COVER SilEET ,
I l
l TITLE: TRPR 33.0, LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM l 1
1 REVISION: 5 DATE: r MAY I 19 77 i
DESCRIBE CHANGES (STEP / CHANGE / REASON):
(FOR REVISION 0, DESCRIBE PURPOSE: PROVIDE
SUMMARY
REVIEW) l
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__ l'- .., :. : l Made Program Revision Record Appendix 1 and added Appendix H, Operationally Significant Administrative Procedures.
I Added annual commitment to review aspects of SOER 96-1 and biennial commitment to conduct PF/JPM 1 Administrator refresher training.
Prepared By: 4/29/97 Date ACCR Review I OPTIONAL: Date Check if desired l Reviewed By: g7tf[f7 Date Approved By: q,pq}
Date Approved By:
y ,y Date I
TR-7.2.1 l Revision 2 (08/17/94) 9705120289 970505 PDR ADOCK 05000301 P PDR
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- -e NUCLEAR POWER BUSINESS UNIT TRPR 33.0 i TRAINING PROGRAMS- NNSR l Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM TABLE OF CONTENTS 1.0 Purpose / Scope 2.0 Definitions I
3.0 Prerequisites / Selection Criteria 4.0 Program Content: Initial Training l
5.0 Program Content: Continuing Training j 6.0 Schedule / Length of Program 7.0 Trainee Evaluation: Initial Training 8.0 Trainee Evaluation: Continuing Training 9.0 Qualification Requirements 10.0 Program Effectiveness Evaluations /Survdllance
! 11.0 Program Administration 12.0 Management Responsibilities i
13.0 Participation Requirements 14.0 References l
15.0 Appendices / Attachments I
' NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 1.0 PURPOSE / SCOPE The goal of the PBNP licensed operator training programs is to produce and maintain well-qualified, licensed operators who contribute to the safe and reliable operation of the plant.
l The program description which follows represents the continuing training component of both TRPR 18.0, " Control Operator Training Program," and TRPR 19.0, " Senior Reactor Operator Training Program." Like the initial components of these programs, the licensed operator requalification program is based on the performance requirements oflicensed operators at PBNP.
l The program is directed at maintaining or improving the knowledge and skills ofjob incumbents.
2.0 DEFINITIONS l
As applied to licensed operator requalification training 2.1 Active License:
! The license held by an individual assigned responsibility for the following:
l (1) performing the ftmetions of a licensed control operator or a licensed senior reactor l operator on shift, with responsibility for completing a minimum of seven 8-hour or five l 12-hour shifts per calendar quarter, and (2) attending and successfully completing the requirements of PBNP's licensed operator requalification training program.
2.2 Annual
Once every calendar year.
! 2.3 Biennial: .
Once every two calendar years. l l I l 2.4 Control Operator (CO):
l Any individual who possesses a reactor operator's license pursuant to Title 10, Code of l Federal Regulations, Part 55, " Operators' Licenses."
r
' 2.5 Diagnostic:
A systematic, logical analysis of plant conditions to identify problems and potential
! causes of these problems, assign probabilities to each potential cause, and develop a logical and prioritized sequence for corrective actions to correct problems or eliminate each potential cause.
2.6 Dynamic Simulator Exam:
A comprehensive examination that uses the simulator in a real-time environment to evaluate the licensed operater's integrated knowledge and skills.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 2.7 Inactive License:
The license held by an individual who attends and successfully completes the requirements of the Licensed Operator Requal training program but is not assigned
- responsibility to perform the functions of a licensed control operator or a licensed senior reactor operator on shift in an active status per 10 CFR 55.
2.8 Job Performance Measure (JPM):
A performance test used to evaluate an individual's knowledge of, and proficiency on,
- - selected tasks.
2.9 Open-Reference Examination:
i An examination during which the examinee may consult controlled materials normally 4
available in the Control Room. Such examinations may include written and static simulator exams.
2.10 Performance Test:
- An evaluation that requires the individual to perform job tasks or other skills according to i job performance requirements and standards, either on the job or in conditions as close to actualjob conditions as possible. Such evaluations may includejob performance measures (JPMs), practical factors (P/Fs), or simulator scenarios.
2.11 Practical Factor (P/F):
Term applied to a job skill addressed in on-the-job training and for which performance testing is the evaluation mode of choice; term may also apply to the evaluation itself.
a 2.12 Requalification Exam:
The tests that comprise the licensed operator requalification examination. Consists of a
! written exam and an operating test made up of dynamic simulator tests and job
- performance measures.
2.13 Segment of Training:
The training presented to licensed individuals during one week of each training cycle.
2.14 Senior Reactor Operator (SRO)
Any individual who possesses a senior reactor operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators' Licenses."
$ 2.15 Static Simulator Exam An exam in which the simulated condition is " frozen" with a plant transient in progress for the purpose of testing the operator's ability to recognize abnormal plant conditions.
2.16 Training Cycle:
The amount of time scheduled to present one segment of training to all licensed individuals.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM i l
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3.0 PREREOUISITES/ SELECTION CRITERI A 3.1 Trainees shall have completed either control operator initial training or senior reactor operator initial training. l 3.2 A newly licensed individual shall enter the requalification program no later than the next cycle following issuance of his/her license by the NRC.
4.0 PROGRAM CONTENT: INITIAL TRAINING See TRPR 18.0, " Control Operator Training Program," and TRPR 19.0, " Senior Reactor )
Operator Training Program."
l 5.0 PROGRAM CONTENT: CONTINUING TRAINING 5.1 Cognizant of the requirements and recommendations of10 CFR 55.59, "Requalification,"
and INPO 86-025, Revision 1, " Guidelines for Continuing Training of Licensed Personnel," the Operations Manager and the Operations Training Coordinator shall define and approve a program that spans a continuous period not to exceed two-years and is ;
geared to the following broad objectives: i 5.1.1 Maintain and upgrade the skills and knowledge necessary to accomplish routine and emergency duties.
5.1.2 Maintain an awareness of the responsibility of the licensed individual for the safe operation of the plant and the consequences ofimproper operation.
5.1.3 Emphasize lessons learned from industry operating experience to prevent repetition of errors.
5.1.4 Correct performance deficiencies amenable to training solutions.
5.1.5 Systematically evaluate individual and team performance to identify areas for improvement.
5.1.6 Maintain an awareness of plant modifications and procedure changes.
5.1.7 Maintain and enhance teamwork and diagnostic skills.
5.1.8 Increase the level of understanding of applied fundamentals presented in initial training.
5.1.9 Enhance the professionalism oflicensed personnel.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM ;
5.1.10 Provide input to plant management for improvements in operating practices, procedures, and plant design.
5.2 The program will include a fixed component and a flexible component. The fixed -
component will be sufficiently broad in scope to systematically review skills and areas of knowledge necessary for safe plant operation. Changes to the fixed component must be authorized by the Operations Training Coordinator in consultation with the Operations !
Manager.
The flexible component, an operational review, will provide a means for updating licensed personnel on changes to procedures, modifications, lessons leamed from l' operating experience, and needs identified from operator feedback and assessments. The content of the flexible component will normally be identified one cycle in advance. ,
5.2.1 The fixed and flexible components of the program constitute a systems apprcach to training and include dynamic simulator and individual skill ,
evaluations which require licensed personnel to demonstrate competency in selected plant evolutions. f i
The plant control manipulations listed in 10 CFR 55.59 C.3, as well as those l addur. sed under INPO ACAD 86-02 , are contained in Appendix A. These ,
manipuladons will be considered for application during development of cycle evaluations. Selected application will be based on operating experience deficiencies, PRA risk dominant systems, components, and events as well as feedback from operator surveys.
i 5.2.2 The two year, long range training plan will include preplanned themes ;
designed to provide coverage of the major operational areas associated with the licensed operator training programs. Frequency of the themes will be based on PRA risk dominant systems, components, and events. Lesson plan content will be designed to address those areas, associated with the theme, ,
where operator experience, assessments, and feedback indicate that emphasis is needed. [ Potential areas for emphasis and review are included in Appendix B.]
The two year schedule will also incorporate specific topics related to commitments or other legal requirements. These are identified in Appendix C and will also contribute to the fixed component of the program.
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. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 l l TRAINING PROGRAMS NNSR l Revision 5 L LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l l i l 5.2.3 Just-in-Time Training (JITT) will run concurrently with, and independent of, l the Licensed Operator Requalification Training program. JITT topics will be identified by Operations Management and the Operations Training l Coordinator and may include necessary training for such issues as procedure j l changes, modification installation, use of temporary equipment, infrequently l l performed tests or evolutions, or items requested by the crew Duty Shift l Superintendent. ;
l These topics are very specific and targeted in nature and will be delivered on j an as needed basis. The JITT administrator will maintain a log of all JITT j "on-line" training occurrences. j 1
5.2.4 Specific skills training for operators will be conducted to address targeted areas for improvement. The skills training may be conducted individually or 1 l
in teams as " mini-scenarios."
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l 5.2.5 Operating experience is tracked by the Regulatory Services group. On a ]
periodic basis they will issue a report documenting applicable in-house and
! industry operating experiences that the Operations Manager and the ]
Operations Training Coordinator may decide to include in training. j l
5.3 A record of program contcel shall be maintained on file by the Operations Training Coordinator for the previous and current calendar year.
i 5.4 Program content shall be reviewed and approved annually by the Operations Manager and the Operations Training Coordinator and updated accordingly.
6.0 SCHEDULE / LENGTH OF PROGRAM 6.1 The Operations Manager and Operations Training Coordinator shall define and approve a program that spans a continuous period not to exceed 2 years. This program will be maintained on file by the Operations Training Coordinator. Flowcharts for development :
! oflong and short range training plans are contained in Appendixes E and F.
6.2 The licensed operator requalification training program will normally be implemented in l six training cycles per year. See Appendix G, Generic Schedule.
L l 6.3 Each training cycle will normally be at least six weeks long to accommodate each of the ,
- six operating crews. If the training cycle does not accommodate a separate training segment for staff personnel, these personnel will attend required lectures throughout the cycle.
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- - NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 l PROGRAM l 7.0 TRAINEE EVALUATION: INITIAL TRAINING See TP PR 18.0," Control Operator Training Program", or TRPR 19.0, Senior Reactor Operator Training Program".
8.0 TRAINEE EVALUATION: CONTINUING TRAINING 8.1 Written and performance-type achievement tests shall be administered to provide answers ;
to such questions as the following: :
8.1.1 To what extent does the trainee possess the knowledge and skills needed to begin instruction?
8.1.2 To what extent has the trainee already achieved the intended learning outcomes of the instruction planned? ,
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8.1.3 On which learning tasks is the trainee progressing satisfactorily?
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8.1.4 On which leaming tasks does the trainee need help? !
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l 8.1.5 Which trainees are having leaming problems that they need remedial work? ;
8.1.6 Which trainees have' mastered the learning tasks to such a degree that they can be considered qualified to continue performing the functions governed and by l
their license independent of direct supervision?
8.2 Segment Evaluations 8.2.1 Evaluations should be in accordance with TIP 8.6, " Written Evaluations" and TIP 8.8, " Simulator Training and Examination" l
8.2.2 Each segment of training will normally be evaluated. The evaluation shall be !
a written evaluation, a p.:rformance-type evaluation, or a combination of both.
l l 8.2.3 The number of evaluation mechanisms utilized in a given cycle will normally be limited to two or less. This concept minimizes the stress associated with multiple assessments and maximizes the training time available during the r cycle.
8.2.4 Enabling leaming objectives may be evaluated through written quizzes, 2
graded assignments, self-assessment instruments, or oral questioning as deemed appropriate.
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' NUCLEAR POWER BUSINESS UNIT TRPR 33.0 j TRAINING PROGRAMS NNSR I l
j Revision 5 i May 1,1997 LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM l j 0.2.5 Unless a lesson in the segment of training is evaluated singly or a j
- performance-type evaluation is administered, a written quiz that addresses the j critical issues covered in that training cycle - - and previous cycles, as j f appropriate -- will normally be administered. l 4 i
- 8.2.6 Specific skills evaluations will be conducted when appropriate to ascertain !
, mastery of a specific skill or evolution that was trained on during that I segments' training. ,
j 8.2.7 Selected cycles will contain a dynamic simulator evaluation. The subject i matter of the dynamic evaluation should be independent of the training i
segment content. Its purpose is to evaluate a crew's performance as a " cold assessment" (i.e., without prior training) _
l Personnel on each crew will be rotated to equitably evaluate each individual at !
i the various positions on the watch team. The Lead Evaluator will ensure this j rotation takes place.
i 8.2.8 Deficiencies in knowledge or performances identified by the segment l 5
evaluation shall be corrected prior to resumption of duties. l Dynamic evaluations may be categorized as "unsat" (one or more critical tasks 4
missed) or " sat" (all critical tasks met). Performance discrepancies are -
addressed in the scenario critique and/or post-dynamic practice session. ;
i-I 8.2.9 A licensed individual may be exempted from a segment evaluation if he or she l
, developed, reviewed, or approved the evaluation instrument in its entirety. l I
i 8.3 Reaualification Exams
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8.3.1 Requalification exams shall be administered annually during the designated examination cycle (s). Reference 10 CFR 55.59. See Appendix G.
, 10 CFR 55.59 requires licensees to pass a comprehensive requalification j' written examination based on the 24 month continuous program, and to pass
- an annual operating test.
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l 4 - NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 I LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 8.3.2 The written examination shall be a two-part examination developed and administered utilizing NUREG 1021, " Operator Licensing Examiner Standards," and TIP 8.6, " Written Evaluations" for guidance. The examination shall contain a representative sampling ofitems testing the knowledge, skills, and abilities needed to perform licensed operator duties.
The knowledge, skills, and abilities shall be identified, in part, from task inventories, the Final Safety Analysis Report, Technical Specifications, system descriptions manuals and operating proced= ,, facility license and ,
license amendments, and licensee event reports.
- a. Section A of the examination shall be an open-referenced, static simulator examination focusing on plant and control systems. j
- b. Section B of the examination shall be an open referenced examination 1 l
focusing on procedure limits and administrative controls. It may be administered in the simulator or a classroom.
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8.3.3 A fonnal sample plan will be produced on a biennial basis in support of the ;
comprehensive requalification written examination. A significant amount of j the material contained in the plan should be assembled on a cyclic basis to maximize efficiency. The sample plan content should contain the following: 1 i
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- a. Cycle Schedules This section contains a detailed summary of the most recent two year implementation of the licensed operator requalification program. It is divided into summaries of each training cycle to include the identifier and title of the training provided, applicable examination topic areas, hours spent in both classroom and simulator, and a comments section for training items that were not considered for the examination. !
- b. Topic Areas This section identifies the major categories (topic areas) considered for the exntnination. Applicable training items from the most recent two year implementation of the licensed operator requalification program should be divided and assembled under the identified topic areas. A summary of i each topic area should include:
- 1. Total hours of training time devoted to the topic area
- 2. % of cycle devoted to the topic area
- 3. % of examination devoted to the topic area Page 8 of 25
NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM
- 4. Test items per examination devoted to the topic area
- 5. Content of each training item included in the topic area
- c. Examination Content This section provides the explicit, documented link between the examination items and the training provided over the most recent two year implementation of the licensed operator requalification program. A table should be developed for each topic area that documents the link and includes the following:
- 1. Exam item identifier
- 2. Related objective
- 3. Content of the exam item
- 4. Time validation
- 5. K/A reference and values
- 6. References used to develop the exam item
- 7. Examination (s) on which the item appears 8.3.4 General Examination Guidelines (Written)
- a. Each section of the written exam should be designed to last 21 hour2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> with both sections approximately equal to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. The validation should have approximately 25% of the total time allocated for examinee review.
- b. There should be a minimum of 15 questions in each section. Static examinations should have 2 50% of the questions related to plant conditions.
- c. A minimum of two versions of each section should be developed. The versions should vary in content by approximately 40%. This ensures that approximately 60% of the questions are seen by each operator and provides an adequate base to determine areas in which retraining is needed to upgrade licensed operator and senior operator knowledge.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 1
- d. The examination should be graded as one entity with a minimum score of 80% required for passing.
E
Areas to consider for SRO level questions include, but are not limited to: ;
- 1. Technical Specifications and their bases i.
- 2. Classification of emergency events
- 3. Directing normal, abnormal, and/or emergency procedures and/or bases for procedural steps
- 4. Radiation limits and controls
- 5. Administrative procedures / requirements
- f. The examination team should consider incorporating 10 to 20% i non-requalification cycle specific examination items.
- g. Individual questions should reference K/A values of 2 3.0.
- h. Versions of the examir.ation will be selected and administered from week to week at the discretion of the licensed operator requalification program !
administrator.
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- i. Exam team members shall sign and adhere to a security agreement stating i that they will not divulge any information about the examination to unauthorized persons and will not participate in any instruction or tutoring of examinees until those examinees have completed their examination. To aid in avoiding compromise, instructors who are on the examination i development team shall wear "NRC Exam Team" identification tags.
- j. Examinees shall sign and adhere to a security agreement stating that they )
will not discuss any aspects associated with the content of the examination i with any examinee until that examinee has completed their examination.
I k. SRO Certs are exempted from taking the examination if they were on the development team.
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' NUCLEAR POWER BUSINESS UNIT TRPR 33.0 i TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM
- 1. Remedial examinations should be developed as required and should be tailored to the individuals who received the failing grade. The content i shall differ from the originally administered examination by 2 50% and i should include questions that focus on those areas where knowledge level was deemed weak. Remedial examinations need not conform to the ,
original topic area percentages stated in the sample plan. !
8.3.5 - The operational examination shall be a two-part test consisting of a dynamic simulator evaluation and a JPM walkthrough developed and administered utilizing NUREG 1021, " Operator Licensing Examiner Standards," and TIP 8.8, " Simulator Training and Examination" for guidance.
8.3.6 General Examination Guidelines (JPM Walk-through)
- a. The examination will consist of 5 JPMs. .
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- i. . Three JPMs will be administered in the simulator. The design should provide for evaluation of a normal, an abnormal, and an j emergency task. !
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- 2. Two JPMs will be administered in-plant. The design should provide for evaluation of a normal and, either an abnormal or emergency task.
- b. No more than 20% of the JPMs . selected for the current examination year should have appeared on the preceding years examination (ex: if 20 JPMs are selected for the current years examination, s4 of those JPMs should have appeared on last year's examination)
- c. A minimum of four JPM examination packages should be developed each year. A comparison of any two packages shall reveal no more than one common JPM.
- d. JPM selection should be based on one or more of the following criteria:
- 1. Task analysis criticality rating of"3"
- 2. New or recently modified system / component l 3. Systems that are the subject of recent NRC LERs
- 4. Systems that are the subject of recent NRC Information Notices Page 11 of 25
- NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSr *ERATOR REQUALIFICATION TRAINING May 1,1997 PROGRi
- 5. Probabilistic Risk Assessment (PRA) risk dominant systems, components, or events
- c. To pass the JPM walk-through examination, each examinee has to successfully complete at least 4 of 5 JPMs. To successfully complete a JPM, the examinee has to complete all critical steps specified in the JPM.
Critical steps are those which when not performed in proper sequence, not performed at the proper time, or not performed correctly willprevent the systemfromfunctioning properly or preclude the successfid completion of the task.
- f. Evaluator Guidance
- 1. Verbal cues are required to provide relevant system information, such as valve position or meter deflection. The evaluator has to be careful to provide the examinee with only the indicatior s that should be readily observed.
- 2. Maintaining a " poker face" when an examinee provides an incorrect response or performs the wrong action is important. Voice inflections indicating incorrect performance or changing the manner in which cues are given are examples of non-verbal communications that should be avoided.
- 3. An evaluator must remain attentive to the examinees actions at all times. This will ensure that the evaluator provides timely cues and detects errors in performance.
- 4. As an evaluator, questioning the licensee during the performance of 1 an examination JPM, to gain insight into what the examinee is thinking, is distracting and may result in prompting or leading the l candidate. Evaluators may ask the examinee questions clarifying the performance of the JPM only after the JPM has been completed.
- 5. The evaluator should be careful to shield any notes or grading from l the examinee to prevent giving the examinee an indication of l j performance, which may either provide a false sense of secunty or I
l increase stress levels.
- 6. When conducting JPMs in the simulator, evaluators should not manipulate any controls or silence alarms associated with the JPM.
This provision does not prohibit evaluators from acknowledging
( non-pertinent alarms or unexpected reactions of other systems not l associated with the task being evaluated.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 )
PROGRAM
- 7. The evaluator should brief the examinees, either individually or as a I group, prior to the start of the walk-through examination. i 1
- g. Versions of the examination will be selected and administered from week to week at the discretion of the licensed operator requalification program administrator.
- h. Exam team members shall sign and adhere to a security agreement stating that they will not divulge any information about the examination to ,
unauthorized persons and will not participate in any instruction or tutoring I of examinees until those examinees have completed their examination. To aid in asoiding compromise, instructors who are on the examination development team shall wear "NRC Exam Team" identification tags. i I
- i. Examinees shall sign and adhere to a security agreement stating that they will not discuss any aspects associated with the content of the examination with any examinee until that examinee has completed their examination.
- j. Rerr dial examinations should be developed as required and should be tailored to the individuals who received the failing grade. The content shall differ from the originally administered examination by 2 50% and should include JPMc that focus on those areas where performance was i deemed weak.
8.3.7 General Examination Guidelines (Simulator Dynamics)
- a. Evaluation requirements:
- 1. Each SRO will be evaluated, in at least one scenario, in the highest crew position for which he is qualified (DSS or DOS)
- 2. Each RO will be evaluated, in at least one scenario, in the highest crew position for which he is qualified (CO)
- b. Scenario overlap from year to year should be limited to 25%. (ex: if 12 scenarios are selected for the current year's examination, s3 of those scenarios should have appeared on last year's examination). Year to year overlap scenarios should be modified to alter equipment out of service and instrument failures to prevent scenario compromise.
- c. A minimum of four dynamic examination packages should be developed each year. A comparison of any two packages shall reveal no more than one common scenario.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR i Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l
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- d. Scenarios may be developed specifically for the examination or selected from the examination scenario bank. Development of examination scenarios should incorporate guidance from ES-604 Att. 3, " Quantitative l and Qualitative Scenario Attributes" to ensure consistency in scope, depth, l and complexity. '
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, e. Examination package development l
- 1. Examination packages should incorporate a variety of malfunctions and events. PRA risk dominant systems, components, and events as well as Appendix A. " Plant Control Manipulations for !
Consideration" should be referenced during development of the !
examination package. l l
4 2. All scenarios should be pre-validated in real time on the simulator l
- 3. Crew personnel rotations should be set prior to administering the examination
- f. The Operations Manager or his surrogate will be assigned to the evaluation team for each Operations crew
- g. An evaluator will be assigned to observe and document individual performance of each of the evaluated positions. The lead evaluator will be assigned to observe and document overall crew performance. Evaluation results will be determined by the evaluation team as a whole, with the Operations Manager or his surrogate having authority for determining the final grade.
- h. Evaluation results may be categorized as follows:
SAT All critical tasks met UNSAT One or more critical tasks not met
- i. Examination packages will be selected and administered from week to week at the discretion of the licensed operator requalification program administrator.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 ;
TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM j
- j. Exam team members shall sign and adhere to a security agreement stating 1 that they will not divulge any information about the examination to i unauthorized persons and will not participate in any instruction or tutoring of examinees until those examinees have completed their exmnination. To aid in avoiding compromise, instructors who are on the examination ;
development team shall wear "NRC Exam Team" identification tags. j
- k. Examinees shall sign and adhere to a security agreement stating that they )
will not discuss any aspects associated with the content of the examination I with any examinee until that examinee has completed their examination.
- 1. Remediation requirements will be determined on a case by case basis and will be approved by the Operations Manager and Operations Training Coordinator.
8.4 Written and operating tests may be administered to licensed personnel to provide feedback relative to program content. If a test is administered for purely diagnostic purposes, individual questions will be graded for group assessment purposes. Individual tests or exams will not be graded nor recorded in individual training records.
9.0 OUALIFICATION REOUIREMENTS The tracking of Active / Inactive status of each operator's license will be maintained by the Operations Manager or his designee. Operations call-up PC 82.8 defines the maintenance procedure for the license tracking log. PBF-2094 is considered the legal record for meeting these requirements.
9.1 Active License To maintain a license active the candidate shall satisfy the requirements / conditions enumerated below annually unless stated otherwise.
9.1.1 The licensee must satisfy the prerequisites / selection criteria of Section 3.0. A copy of the individuals license shall be on file with PBNP Training.
9.1.2 The licensee must complete all applicable segment evaluations.
- a. The cycle quiz passing criterion is 80%.
- b. The dynamic simulator evaluation passing criterion is SAT"
- c. Skills evaluation passing criterion is in accordance with the associated evaluation guidance.
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 l
LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM i
- d. An individual with an active license who fails a segment evaluation shall
, not perform licensed duties until remediation has been satisfactori!y l completed.
- e. Remediation for cycle quiz scores from 70.0% - 79.9% shall consist of a !
l thorough review of missed items. All other remediation requirements will be determined on a case by case basis and will be approved by the Operations Manager or Operations Training Coordinator.
l l 9.1.3 The licensee must pass the requalifications exams of Section 8.3.
- a. The written examination passing criterion is 80%.
- b. The dynamic simulator evaluation passing criterion is " SAT" l'
- c. The JPM passing criterion is 80%.
l .
- d. An individual with an active license who fails either the written examination or the operating test shall not perform licensed duties until remediation has been satisfactorily completed,
- e. Requalification examination failures (written and operating), require reexamination in addition to remediation.
9.1.4 The licensee shall perform the functions authorized by his/her license on shift for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter.
! This on-shift time shall be documented on PBF-2094, "NRC License: Shifts to Maintain Active Status."
l 9.1.5 The licensee shall have a medical examination pursuant to 10 CFR 55.21 biennially of the anniversary date of the most recent exam. A copy of NRC-396, " Certification of Medical Examination by Facility Licensee," shall be on file with PBNP Training. Medical examinations are administratively controlled by NP 1.10.1, " Medical Certification and Record Keeping for j Licensed Personnel."
9.2 Inactive License To maintain a license inactive the candidate shall satisfy the requirements / conditions !
enumerated below annually unless stated otherwise. :
9.2.1 The licensee must satisfy the prerequisites / selection criteria of Section 3.0. A copy of the individuals license shall be on file with PBNP Training.
Page 16 of 25 l
NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5
- LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM
- 9.2.2 The licensee must complete all applicable segment evaluations.
- a. The cycle quiz passing criterion is 80%.
- b. The dynamic simulator evaluation passing criterion is " SAT"
- c. Skills evaluation passing criterion is in accordance with the associated evaluation guidance.
t d. Remediation for cycle quiz scores from 70.0% - 79.9% shall consist of a l thorough review of missed items. All other remediation requirements will be determined on a case by case basis and will be approved by the Operations Manger or Operations Training Coordinator.
3 9.2.3 The licensee must pass the requalifications exams of Section 8.4.
- a. The written examination passing criterion is 80%.
i b. The dynamic simulator evaluation passing criterion Satisfactory.
- c. The JPM passing criterion is 80%.
- d. Requalification examination failures (written and operating), require reexamination ir. addition to remediation.
9.2.4 The licensee shall have a medical examination pursuant to 10 CFR 55.21 biennially of the anniversary date of the most recent exam. A copy of NRC-396, " Certification of Medical Examination by Facility Licensee," shall be on file with PBNP Training. Medical examinations are administratively controlled by NP 1.10.1, " Medical Certification and Record Keeping for Licensed Personnel."
9.3 Activating an Inactive License 1 9.3.1 An individual with an inactive CO license may change the license to an active status by completing TRQM 18.32," Qualification Card: Inactive License."
Reference 10 CFR 55.53(f). Successful completion of TRQM 18.32 requires that a licensee certify that his/her qualifications and status of the license re current and valid and that the licensee has completed 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (live,8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> watches) under instruction. This includes a complete tour of the plant and all i required shift turnover procedures.
Page 17 of 25
' NUCLEAR POWER BUSINESS UNIT TRPR 33.0 ,
TRAINING PROGRAMS NNSR j Revision 5
) LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1F PROGRAM l 1
9.3.2 An individual with an inactive SRO license may change the license to an active status by completing TRQM 19.32, " Qualification Card: Inactive .
l License." Reference 10 CFR 55.53(f). Successful completion of TRQM 19.32 reauires that a licensee certify that his/her qualifications and .
. status of the Ikense are current and valid and that the license has completed 40 l hours (five,8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> watches) under instruction. This includes a complete tour j l of the plant and all required shift tumover procedures. ;
9.4 Expiration of License l
9.4.1 An individual's license shall expire six years after the date ofissuance, upon termination of employment with Wisconsin Electric, or upon determination by 4
Wisconsin Electric that the individual no longer needs to maintain a license.
1 9.4.2 Wisconsin Electric shall request the NRC to terminate the license of any
]
individual who does not continue to meet regulatory requirements.
i 10.0 PROGRAM EFFECTIVENESS EVALUATIONS / SURVEILLANCE
'10.1 Training and/or Operations personnel shall perform the following program effectiveness i surveillance in accordance with the requirements of the training procedure identified:
1 10.1.1 Trainee Reactions -- TIP 10.3, Trainee Reaction Forms 10.1.2 Manager / Supervisor Observations -- TIP 10.1, Performance Assurance j l
System Administration
.d 10.1.3 Instructor Evaluation -- TIP 10.1, Performance Assurance System
, Administration 10.1.4 PF/JPM Administrator Evaluation -- TIP 9.5, On-The-Job Training and Task Qualification 10.1.5 Exam item Analysis -- TIP 8.6, Written Evaluations 4
- 10.1.6 Training Advisory Committee (TAC)-- TRNG 10.0, Management Oversight and Systematic Evaluation of Training Effectiveness 10.1.7 Simulator Evaluations -- TIP 8.8, Simulator Training and Examination.
10.2 Each crew will provide feedback on the content of the segment's training. The crew will identify strengths and weaknesses of content, delivery, forum, crew participation and efTectiveness. These crew training effectiveness reviews are an integral part of assessing program effectiveness.
Page 18 of 25
i ' NUCLEAR POWER BUSINESS UNIT TRPR 33.0 ,
TRAINING PROGRAMS NNSR I Revision 5 i LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l 10.3 The Operations Training Coordinator will write an End-of-Cycle (EOC) Report following each full training cycle. The EOC Report will summarize training activities for the cycle as well as identify strengths and weaknesses for each of the operations training programs.
, This report will reflect the input gathered from various sources such as management
! oversight and observation, crew training effectiveness reviews, training observations, l procedure feedback, simulator dynamics and TAC open items.
The EOC Report should be used as a continuous assessment tool to provide Operation / Training management a systematic approach to enabling training plan and l program changes. j 11.0 PROGRAM ADMINISTRATION 11.1 The training program administrator for the licensed operator requalification (LOR) training program is responsible for the following:
11.1.1 Scheduling instructors, trainees, classrooms, and simulator time l 11.1.2 Ensuring that evaluations are prepared and administrated as prescribed 11.1.3 Ensuring that program effectiveness surveillances are performed within the frequency prescribed 11.1.4 Ensuring that an analyzer table is run to systematically track trainee attendance, make-up and program completion requirements. This report will become part of the end-of-cycle report and will be regularly updated. Trainees should normally complete make-up assignments within one cycle following the missed training.
11.1.5 Ensuring that program completion audits are performed 11.1.6 Ensuring that NRC licensing deadlines and other requirements relative to license renewal are satisfied. The Operations Training Coordinator is responsible for assuring license renewals are formally tracked.
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- - ,. . = - - . - - - - .- . . . - -- - . - . .
NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 12.0 MANAGEMENT RESPONSIBILITIES l
l Primary responsibility for the continual, systematic evaluation of LOR training quality,
! completeness, and effectiveness rests with the Operations Manager. A Training Advisory Committee (TAC) as defined by TRNG 10.0, " Management Oversight and Systematic l
Evaluation of Training Effectiveness," exists to facilitate work group involvement, steering, and I oversight of the operator training and qualification program. The Operations TAC represents a partnership between Operations and PBNP Training, with each partner delivering the i considerations enumerated below.
l 12.1 Operations:
12.1.1 Operations management will establish performance standards: present, discuss, and reinforce expectations during both initial and continuing training; and verify these standards / expectations during training evaluation and the qualification process. j 12.1.2 Operations management will periodically observe classroom training. l simulator training, and on-the-job training and task performance evaluation j activities in progress to verify that group and personnel needs are met, 1 performance standards are reinforced, and participants are challenged. l l
12.1.3 Operations management will periodically observe in-plant task performance to verify that training is effective.
12.1.4 Operations management will ensure that personnel attend required training or participate in timely make-up. j 12.1.5 Operations management will ensure that trainees conduct themselves in a professional manner.
12.1.6 Operations management will ensure that the licensed operator requalification J
program is carried out in accordance with the provisions of TIP 9.5, "On-the-Job Training and Task Qualification," and that trainees complete designated training and qualification requirements prior to being assigned to work independently of direct supervision.
12.1.7 Operations management will ensure that personnel who conduct on-the-job training or task performance evaluations are cognizant of the policies, procedures, methods, and standards governing the effective conduct of these
, activities.
l Page 20 of 25
- NUCLEAR POWER BUSINESS UNIT TRPR 33.0 i TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 12.1.8 Operations management will ensure that on-the-job training is conducted by
. qualified individuals using valid methods, approved material and a planned and logical instructional sequence.
12.1.9 Operations management will ensure that task performance evaluation is conducted by only qualined individuals using valid evaluation methods, that trainee performance is measured against established standards prior to task or l job qualincation, and that remediation and reevaluation are provided when j performance standards are not met satisfactorily.
12.1.10 Operations management will regularly evaluate the technical competencies of ,
. instructors in all applicable settings.
. 12.1.11 Operations management will provide subject matter experts, as appropriate and as needed, to help develop a valid task list as the basis for the licensed operator training and quali6 cation programs.
Trainine 4
12.2 12.2.1 Training management will ensure that the Training Manager, Training Coordinators, instructors, and program development personnel possess and maintain the educational, technical, and experience quali6 cations required for their respective positions.
12.2.2 Training management will maintain an instructional skills training program j that develops the necessary instructor capabilities to fulnll training program 1
requirements in all applicable training settings.
12.2.3 Training management will ensure that instructors are provided with adequate f
time to prepare to deliver effective and consistent training.
12.2.4 Training management will regularly evaluate the instructional skills and evaluation techniques ofinstructors in all applicable settings.
12.2.5 Training management will ensure continual instructor development to maintain or improve n'eeded technical and instructional knowledge and skills and to address weaknesses identined through evaluations ofinstructor performance.
12.2.6 Training management will ensure that new tasks and modified tasks selected for training are analyzed to identify new knowledge and skills to be included in the training program.
Page 21 of 25
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NUCLEAR POWER BUSINESS UNIT TRPR 33.0
! : TRAINING PROGRAMS NNSR Revision 5 4
' LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM
-12.2.7 Training management (vill ensure that leaming objectives are derived from an analysis ofjob performance requirements, that they are used to establish l essential training content, and that they are sequenced to facilitate the ]
progression of trammg. ,
i 12.2.8 Training management will ensure that job related knowledge is provided l through effective classroom training, laboratory training, simulator training, or I self-study.
-12.2.9 . Training management will ensure that self-study and individualized j instruction, when used, provide the trainee with suflicient guidance and j supporting materials for achieving the leaming objectives.
1 12.2.10 Training management will ensure that lesson plans and other training material i used for classroom, laboratory, simulator, self-study, and on-the-job training j are accurate, support the learning objectives, and promote effective delivery of j instruction.
12.2.11 Training management will ensure that achievement test items are based on the )
learning objectives and effectively assess trainee knowledge or level of !
performance.
J l
12.2.12 Training management will ensure that trainee mastery oflearning objectives is evaluated regularly using valid written, oral, and/or performance measures of - !
achievement and that remediation and reevaluation are provided when performance standards are not met satisfactorily.
12.2.13 Training management will encourage instructors to use instructional-techniques that promote mastery of the learning objectives and encourage trainee particiption.
12.2.14 Training management will provide assistance to and monitoring of subject matter experts (SMEs) used as instructors to ensure quality training. j 12.2.15 Training management will maintain training records to support management i information needs and to provide required historical data.
i 12.2.16 Training management will maintain a matrix cross-referencing tasks to i training material to confirm training program content current. j 12.2.17 Training management will write an End-of-Cycle Report following each full training cycle and provide results to the Operations Manager.
Page 22 of 25
i NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 13.0 PARTICIPATION REOUIREMENTS ;
i 13.1 Individuals enrolled in the licensed operator requalification training program shall attend I all scheduled classroom and simulator training unless incapacitated by illnes.; or specifically excused for some other good cause. Planned absences shall be authorized by the Operations Manager. See Appendix D for attendance requirements. )
13.2 Individuals who miss - or anticipate missing - any portion of a training segment in the i week scheduled shall attend that training in another training week. In the event that this l is not possible, the missed training shall be made up in accordance with the lesson plan's :
make-up contingencies. Trainees should normally complete make-up assignments within l one cycle following the missed training. The Operations Manager reserves the authority l to exempt an individual, if emergent, IAW TIP 9.2. Make-up of continuing training that j is not governed by a lesson plan shall be determined by the Operations Manager in l consultation with Training. l 13.3 In addition to being physically present for scheduled training, licensed operators shall l exhibit professionalism by conducting themselves in the following manner: ;
i 13.3.1 Being mentally alert, attentive, and receptive to the training being provided, 1
13.3.2 Participating in the training by developing a questioning attitude that stimulates discussions and promotes understanding of the training material.
13.3.3 Completing training assignments, exercises, and laboratories in a manner that promotes learning.
13.3.4 Maintaining personal integrity while completing quizzes, tests, examinations, and other measures of achievement.
13.3.5 Giving candid and constructive feedback on training program and material weaknesses.
1 13.3.6 Accepting personal responsibility for completing all training and requalification requirements. i 13.3.7 Using the time given over to requalification exam preparation exclusively for the purpose for which it is intended. !
13.4 Individuals may be granted exemptions from training when supported by a documented assessment of prior education, training, and experience in accordance with the provisions ;
of TIP 9.2, " Training Exemptions." Generally, exemptions from training requirements will not include exemptions from qualification requirements.
Page 23 of 25
NUCLEAR POWER BUSINESS UNIT TRPR 33.0
- TRAINING PROGRAMS NNSR 4 Revision 5 l LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM
14.0 REFERENCES
14.1 Title 10, Code of Federal Regulations, Part 55 14.2 NUREG 1021, Operator Licensing Examiner Standards, Revision 7.
14.3 Institute of Nuclear Power Operations, INPO 86-025 (Revision 1), Guidelinesfor Continuing Training ofLicensedPersonnel. Atlanta: Author,1989.
14.4 National Academy for Nuclear Training, ACAD 85-006, Principles ofTraining System i Development. Atlanta: Institute of Nuclear Power Operations,1993 ;
14.5 National Academy for Nuclear Training, ACAD 92-004, Guidelines)or the Conduct of ,
Training and Guahylcation Activities. Atlanta: Institute of Nuclear Power Operations, !
1992.
14.6 National Academy for Nuclear Training, ACAD 91-015, The Objectives and Criteriafor l Accreditation of Training in the Nuclear Power Industry. Atlanta: Institute of Nuclear .
Power Operations,1991. ]
l 14.7 National Academy for Nuclear Training, ACAD 91-006. Guidelinesfor On-the-Job Training and Evaluation. Atlanta: Institute of Nuclear Power Operations,1991. 1 l
14.8 National Academy for Nuclear Training, ACAD 91-012, Guidelinesfor Training and Guahylcation ofLicensed Operators. Atlanta: Institute of Nuclear Power Operations, 1991.
15.0 APPENDICES / ATTACHMENTS l
15.1 Appendix A, Plant Control Manipulations for Consideration 15.2 Appendix B, LOR Fixed Component Suggested Topic Areas 15.3 Appendix C, Long Range Training Plan Required or Commitment Related Topics 15.4 Appendix D, Attendance Requirements ;
15.5 Appendix E, Long Range Training Plan Development 15.6 Appendix F, Short Range Training Plan Development l 15.7 Appendix G, Generic LOR Schedule 15.8 Appendix H, Operationally Significant Administrative Procedures Page 24 of 25
' - NUCLEAR POWER BUSINESS UNIT TRPR 33.0
. TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l 15.9 Appendix I, Synopsis: Program Revision Record l
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- NUCLEAR POWER BUSINESS UNIT TRPR 33.0
- i. TRAINING PROGRAMS NNSR l Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM APPENDIX A PLANT CONTROL MANIPULATIONS FOR CONSIDERATION .
! Code of Federal Regulations l
l 55.59CFR(A) 55.59CFR(I) 55.59CFR(S) plant or reactor startup with loss of electrical power, or inability to drive rods establish IlUR degraded power sources 55.59CFR(B) 55.59CFR(J) 55.59CFR(T) plant shutdown loss of core coolant flow / natural conditions requiring use of circulation emergency boration 55.59CFR(C) 55.59CFR(K) 55.59CFR(U) manual control of SGWL loss of feedwater, normal and fuel clad failure or high RC >
during startup and shutdown emergency activity or off-gas 55.59CFR(D) 55.59 R(L) 55.59CFR(V) boration or dilution during loss of service water turbine or generator trip power' operation 55.59CFR(E) 55.59CFR(M) 55.59CFR(W) 210% power changes in loss of shutdown cooling malfunction of auto control manual rod control system affecting reactivity 55.59CFR(GI) 55.59CFR(N) 55.59CFR(X)
LOCA, significant S/G tube loss of component cooling malfunction of RC leaks system or to a component pressure / volume control system 55.59CFR(G2) 55.59CFR(0) 55.59CFR(Y)
LOCA,inside and outside loss of normal feedwater or reactor trip primary containment system failure 55.59CFR(G3) 55.59CFR(P) 55.59CFR(Z)
LOCA, large and small, w/ leak loss of condenser vacuum main steam line break (inside or rate determination outside containment) 55.59CFR(G4) 55.59CFR(Q) 55.59CFR(AA)
LOCA, saturated RC response loss of protective system Nl failure channel 55.59CFR(II) 55.59CFR(R) loss ofIA mispositioned or dropped rods 1
- _ - . - - _ _ _ - _~ . . -- - . . . . . _ . . -.- .- ._ __. -
l NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR j Revision 5 l LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 l PROGRAM ACAD 86-025
. switch feedwater control from . boron control malfunction . PORV or Safety valve stuck open !
manual to auto
) . place into or remove from . premature criticality . ATWS
, service major components or systems
. inadvertent engineered safety . loss of heat sink . natural events (earthquake, )
i features actuation tornado, etc.) -
. failure of engineered safety . station blackout . failure of turbine extraction steam
- feature to actuate non-return valves
. RCP trip . failure of containment isolation . inadvertent main steam or
- feedwater isolations
. control room evacuation . containment pressure or . failure of turbine generator temperature high
. RCP seal failure . inadvertent containment isolation . excess feedwater transient i
e condensate pump or system . inadvertent containment spray j failure
. generator stator cooling failure e accidental liquid or gaseous release
. loss of annunciator pwr 4
e 2
NUCLEAR POWER BUSINESS UNIT TRPR 33.0
. TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM 3
APPENDIX B
- LOR FIXED COMPONENT SUGGESTED TOPIC AREAS i
(these areas reflect the general requirements of 10 CFR 55.59 as well as the guidance ofINPO 86-025 rev.I this is not an all i inclusive list) 10 CFR 55.59 INPO 86-025 rev.1. cont. i i
+ theory and principles of operation . case studies of operational experience ;
, l j . general and specific plant operating characteristics e severe accident management l
3 . plant instrumentation and control systems e administrative procedures, conditions and limitations
. plant protection systems . facility design and license changes
. engineered safety systems l
. normal, abnormal and emergency operating . site emergency plan procedures l
. radiation control and safety . industrial safety i . technical specifications . EOP and CSP basis steps i
9
. applicable portions of title 10, chapter I, Code of . supervisory skills training l 4 Federal Regulations !
1 a 1 d
INPO 86-025 rev. I
- 1
. applied heat transfer, fluid flow and thermodynamics . teamwork, leadership communications and diagnostics
- '. features of facility design . major operational evolutions
. plant chemistry control
. fuel handling
. rtactor core design parameters and limits
. transient and accident analysis and control, including accident mgt.
4
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- TRPR 33.0
' NUCLEAR POWER BUSINESS UNIT TRAINING PROGRAMS NNSR I Revision 5 l l LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 l PROGRAM 1
APPENDIX C j LONG RANGE TRAINING PLAN REQUIRED OR COMMITMENT RELATED TOPICS l
Commitment References Freauencv Complete task P7311 AOT, Wear NUIEG 0041 Annual SCBA 10 CFR 20.103 l
Review and update training, as AM 3-1, Corporate Water Chemistry Annual l appropriate, on NP 3.2.2, Primary Policy Chemistry Monitoring Program and NP 3.2.3, Secondary Chemistry Monitoring Program Review Conservative Decision SOER 94-01 (Salem) Annual j Making Operating Philosophy NUTRK: SOER 94-01-04A/l j i
Conduct Operational Examination 10 CFR 55.59 Annual (Dynamics /JPMs) ,
Conduct Annual Danger Tag NP 1.9.15 Annual j Refresher Training Review key aspects of SOER 96-1 SOER 96-1 Annual l
Conduct Written Examination 10 CFR 55.59 Biennial (Static / Limits & Controls)
Conduct evaluation of shift NUTRK: TAC-OPS-94-06, SOER Biennial ;
management turnover. DSS, DOS, or 94-01-04All l Third RO outside of the simulator control room at commencement of the dynamic evaluation Review administrative areas NUTRK: NRC 96EC #20 Biennial significant to daily operation of the See Appendix H for procedure l plant during each two year operations listing.
l training plan i
Refresher training on PF/JPM OM 2.14, PF/JPM Administrator Biennial Administrator responsibilities 1
NUCLEAR POWER BUSINESS UNIT TRPR 33.0 ;
TRAINING PROGRAMS NNSR l Revision 5 l LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 l PROGRAM APPENDIX D ATTENDANCE REQUIREMENTS FOR PERSONNEL ENROLLED IN THE LOR PROGRAM (OR APPLICABLE PORTIONS)
SCHEDULED TRAINING -
1 l
Flexible Component l Skills Fixed Simulator SRO QE PSU Evaluation Component Dynamic Licenses Active / Inactive i
ROs X X X X X i
SROs X X X X X X i
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- Skills may be required by the OPT SRO Certs if an individual administrates P/F, JPM or skill j evaluations. !
l- **May be required to attend depending on the subject matter. Attendance requirement to be determined i
! by Operations Manager / Operations Training Coordinator.
- ** Participation described for program management purposes only.
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4 NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 l LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM APPENDIX E i 3-0*g
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' TRAINING PROGRAMS NNSR i Revision 5 I LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 i PROGRAM APPENDIX G GENERIC LOR SCHEDULE Cycle 1 Training Cycle Cycle 2 Pre-outage training cycle with requalification written exam (if administered) ,
Cycle 3 Unit 1 Outage (No Scheduled Training)
Cycle 4 Training Cycle l
Cycle 5 Training Cycle 1 Cycle 6 Pre-outage Training Cycle with requalification operational /JPM Exams Cycle 7 Unit 2 Outage (No Scheduled Training)
, Cycle 8 Training Cycle l
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i NUCLEAR POWER BUSINESS UNIT TRPR 33.0 l TRAINING PROGRAMS NNSR l Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM {
i APPENDlX II i OPERATIONALLY SIGNIFICANT ADMINISTRATIVE PROCEDURES Nuclear Orcanization Manual (NOM): l None l
Administrative Manual (AM):
i
- 1. AM 3-3. At Power Primary-to-Secondary Leakage Monitoring Program l r
1 Nuclear Power Business Unit Procedures Manual (NP):
- l. NP 1.1.4, Procedure Use and Adherence
- 2. NP 1.2.2, Technical Procedure Classification, Review, and Approval
- 3. NP 1.2.3, Tcmporary Changes j '4. NP 1.2.4, Procedure Documentation Requirements
! 5. NP 1.2.6, Infrequently Performed Tests or Evolutions
- 6. NP 1.6.4, Verbal Communication Procedure l 7. NP 1.6.6, Work Duration Restrictions !
- 8. NP 1.9.15, Danger Tag Procedure i
- 9. NP 2.3.3, Work Control Center i
- 10. NP 3.2.2, Primary Water Chemistry Monitoring Program
- 11. NP 3.2.3, Secondary Water Chemistry Monitoring Program ;
- 12. NP 5.3.7, Operability Determinations l
- 13. NP 7.3.1, Temporary Modifications l
- 14. NP 8.1.1, Work Order Processing
- 15. NP 10.1.1, TS Equipment OOS/ Voluntary Entry into an LCO l 1 l
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- NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 5 ,
LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l APPENDIX II, (cont.)
Operations Manual (OM):
- 1. OM 1.1, Conduct of Plant Operations
- 2. OM 3.7, Emergency Operating Procedures Use and Adherence
- 3. OM 3.12, Control of Equipment and Equipment Status
- 4. OM 3.17, Independent Check Guidelines
- 5. OM 3.18, Operations Administrative Limits
- 6. OM 3.19, Reactor Coolant System Leakage Determination
- 7. OM 3.20, MOV/AOV Operation and Maintenance Guidelines
- 8. OM 3.26, Use of Dedicated Operators
- 9. OM 3.27, Centrol of Fire Protection and Appendix R Safe Shutdown Equipment
- 10. OM 3.29, Pre-Job and Post-Job Briefings
- 11. OM 4.1.1, Post-Trip Review
- 12. OM 4.2.2, inservice Tests
- 13. OM 5.4.1, Operations Group Periodic Testing and Surveillance
- 14. OM 5.4.4, Control of Posted Plant Information
'15. OM 6.1, Perfonnance Assessment Program
' '* TRPR 33.0
, NUCLEAR POWER BUSINESS UNIT TRAINING PROGRAMS NNSR Revision 5 LICENSED OPERATOR REQUALIFICATION TRAINING May 1,1997 PROGRAM l APPENDIX 1 SYNOPSIS: PROGRAM REVISION RECORD l
Revision 0: Created a separate program description for LOR. Formatted in response to the INPO ,
PBH-RSAQ2-1,(Operations ASER conducted December 13-17,1993) i Revision 1: Revised program to reflect improvements related to NRC 1R 94-003, PBL 94-0296 and Audit A-P-94-20; additional improvements made to provide a more systematic approach to training.
Revision 2: Revised program to expand upon the current systematic approach to training. Revision included: clarifying definitions, describing methodology for demonstrating competency in selected evolutions, adding guidance for development and conduct oflicense l' requalification examinations, and adding remediation requirements for cycle evaluations.
Revision items related to NRC Inspection Report 50-266/95002( ); i
'50-301/95002( . (LOR Inspection conducted February 13-17,1995).
Revision 3: Updated program to reflect changes in current practices. Revision included elimination of pass with remediation category, clarifying LRTP expectations, clarifying badging requirements, and added guidance requiring re-examination for requalification exam ,
failures, as well as making numerous administrative / clarification corrections.
Revision 4: Added " Review administrative areas significant to daily operation of the plant" to ;
Appendix C per NUTRK: NRC 96EC #20. Added annual requirement to conduct danger ;
tag refresher training to Appendix C to meet NP 1.9.15 requirement.
Revision 5: Made program revision record Appendix 1 and added Appendix II, Operationally Significant Administrative Procedures. Added annual commitment to review aspects of i SOER 96-1 and biennial commitment to conduct PF/JPM Administrator refresher l training. ;
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POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS Commitment ID Number 75 i I
Commitment Description Revise the initial and requalification operator trauung plans to include a review of the admmistrative procedures i identified as significant to daily operation of the plant during each two year operations trauung plan. ;
This commitment is also Enforcement Conference Commitment Item # 20.
Review Methodology Review the list ofidentified admmistrative procedures having significance to daily plant operation.
]
Verify revisions to both initial and requalification operator training plans to ensure they include or reference the ,
specified admmistrative procedures and that the requalification program will capture this commitment each two l years. '
Review Results As of January,1997, a change to the Operator Requalification Training Program, TKPR 33.0 Rev. 3 October 16, 1996, was submitted and reviewed on 12/26/96 and approved on 1/9/97. This change captured the commitment for both the 1997 requali6 cation training (see cycles 97-4, 97-5, and 97-6) and the longer term two year cyclic plan (see proposed change to Appendix C of TRPR 33.0)
Additionally as of January 1997, a NUTRK action item was initiated on 12/26/96 to ensure that this commitment is incorporated into the initial programs admmistrative training courses (TRCR 61.0, TRCR 68.0, and TRCR 86.0).
The list of admmistrative procedures significant to daily plant operations was provided to the Training Dept, in memo NPM 97-0190, dated 4/15/97.
On May 1,1997, Rev.12 of TRCR 86.0, " Administrative", was issued which captures the administrative procedures -
identi6cd in NPM 97-0190 as required for initial operator trammg. l l
.i Also on May 1,1997, Rev. 5 of TRPR 33.0, " Licensed Operator Requalification Trauung Program" was issued l i
which captures the admininrative procedures identified in NPM 97-0190 as required for operator requalification training. l l
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t POINT BEACH UNIT 2 RESTART COMMITMENT INDEPENDENT REVIEW RESULTS i
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a Commitment ID Number 75 i
Recommendations ;
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. i There are no recommendations. Based on this Independent Review, there are no items associated with this Restart - .j Commitment # 75 which would impede Unit 2 Restan.
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