ML20217P550

Rev 6 to Trpr 33.0, Licensed Operator Requalification Training Program

ML20217P550
Person / Time
Site:	Point Beach
Issue date:	07/15/1997
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20217P221	List: ML20217P550 NPL-97-0518, Forwards Requested Info Concerning Operational Exam Being Conducted at Plant During Week of 970908
References
TRPR-33.0, NUDOCS 9708280088
Download: ML20217P550 (71)

Text

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PolNT llEACil NUCLEAR PLANT TRAINING PROGRAM COVER SilEET ,

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TITLE; TRPR 33 0, LICENSED OPERA f0R REQUAliflCATION TRAINING PROGRAM i REVISION: 6 DATE:

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DESCRIBE CllANGES (STEP: CHANGE / REASON):

(FOR REVISION 0. DESCRIBE PURPOSE: PROVIDE SUh1 MARY REVIEW) -

i Resised section 5.2.5 description of how operating esperience is evaluated for training, j

- Added new section 8,3 (renumbered subsequent sections) to describe criteria for independent grading of tests aah scores between 75 83% and actions for UNSATor failed etaluationt

. Deleted diseunion of remediation for quiz failures with scores betw een 70-80% is a through review of quiz.

Added information under section 13.2 to describe policy for make up of missed requal training.

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~~ Date ACCR Review M Al[A OPTIONAL: 5 Date Check if desired

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Reviewed Dr g Tpi[ng Coordinator D3

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/ T/ainin'g Manager M / Date 9708290088 970715 PDR. ADOCK 05000266 4 V- PDR ,-

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. TRAININO PROGRAhlS NNSR l Revision 6 i LICENSED OPERATOR REQUALIFICATION July 15,1997 l TRAININO PROGRAh!  !

TAllLE OF CONTENTS 1.0 Purpose / Scope t

6 2.0 Definitions (

t 9-l 3.0 Prerequisites / Selection Criteria 4.0 - Program Content: Initial Training

) ,

e 5.0 Program Content: Continuing Training 6.0 Schedule / Length of Program i

7.0 Trainee Evaluation: Initial Training 8.0 Trainee Evaluation: Continuing Training 9.0 Qualification Requirements  !

1 10.0 Program Effectiveness Evaluations / Surveillance j

i 11.0 Program Administration i

12.0 hlanagement Responsibilities 13.0 . Participation Requirements ,

14.0 References i5.0 Appendices / Attachments i

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• NUCLEAR POWER BUSINESS UNIT TRPR 33.0

. TRAINING PROGRAMS NNSR l Revision 6 LICENSED OPER4 TOR REQUALIFICATION July 15,1997 TRAINING PROGRAM  ;

i

10 EURp0SE/ scope )

! l The goal of the PBNP licensed operator training programs is to produce and mainta!n  :

-well qualified, licensed operators uho contribute to the safe and reliable operation of the plant.

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. ,

The program is directed at rnaintaining or improving the knowledge and skills ofjob incumbents.

2.0 DEFINITIONS i

4 f

As applied to licensed operator requalification training 2.1 Active I icense:

, The license held by an individual assigned responsibility for the following:

l (1) performing the functions of a licensed control operator or a licensed senior reactor operator on shill, with responsibility for completing a minimum of seven 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shif ts 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,-

I 2,3 Diennial:

Once every two calendar years, i

2A Control Ooerator (COk Any individual who possesses a reactor operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operators' Licenses."

2.5 Diacnostic

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 i logical and prioritized sequence for corrective actions to correct problems or eliminate each potential cause. l

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., ,, NUCLEAR p0WER BUSINESS UNIT TRPR 33.0 TRAININO PROGRAhts NNSR

- Revision 6 I LICENSED OPERATOR REQUALIFICATION July 15,1997  !

TRAINING PROGRAh!

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)O 2.6 Dynamic Simulator Exam: .

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i A comprehensive examination that uses the simulator in a real time environment to i i evaluate the licensed operator's integrated knowledge and skills.  !

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2.7 Inactive License: i The license held by an individual who attends and successfully completes the i

~ 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 l reactor operator on. shift in an active status per 10 CFR 55.

r i 2.8 Job Performance hieasure (JPNIP ,

A performance test used to evaluate an individual's knowledge of, and proficiency on,

• selected tasks.

2.9 Or'en Reference Examination:

i An examination during which the examinee may consult controlled materials normally available in the Control Roorn. 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 '

job performance requirements and standards, either on the job or in conditions as close to

' actualjob conditions as possible. Such evaluations may include job performance i measures (JPhls), practical factors (P/Fs), or simulator scenarios.

2.11 Practical Factor (P/Fh t

Term applied to ajob 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, 2 2.12 Reaualification 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 -Seement of Traininc:

The training presented to licensed individuals during one week of each training cycle.  !

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", NUCI. EAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAh1S NNSR Revision 6 LICENSED OPERATOR REQUAllFICATION July 15,1997 TRAINING PROGRAh1 k

2.14 Senior Reactor Orserator 6l{0.)

Any individual who possesses a senior reactor operator's license pursuant to Title 10, Code of Federal Regulations, Part 55," Operators' Licenses."

2.15 S.latic SimuIatorlum 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 conditior.s.

2.16 Trainine Cvele:

The amount of time scheduled to present one segment of training to all licensed individuals.

3.0 PREREOUISITES/ SELECTION CRITERIA 3.1 Trainees shall have completed either control operator initial training or senior reactor operator initial training.

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 PROGRANI CONTENT: INITI AL TRAINING See TRPR 18.0 " Control Operator Training Program." and TRPR 19.0," Senior Reactor Operator Training Program."

5.0 1%Qf_dMht CONTENT: CONTINUING TRAININfG 5.1 Cognintnt of the requirements and recommendations of 10 CFR 55.59,"Requalitication,"

and INPO 86 025, Revision 1," Guidelines for Continuing Training of Licensed Personnel," the Operations hinnager 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:

5.1.1 hiaintain and upgrade the skills and knowledge necessary to accomplish routine and emergency duties.

5.1.2 hiaintain an awareness of the responsibility of the licensed individual for the safe operation of the plant and the consequences ofimproper operation.

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NUCLEAR POWER BUSINESS UNIT TRPR 310 TRAINING PROGRAhlS NNSR Revision 6 LICENSED OPERATOR REQUAllFICATION July 15,1997 TRAINING PROGRAh!

5.1.3 Emphasize lessons learned from industry operating exper s .e to prevent repetition of errors.

5.1.4 Correct performance deliciencies am rnable to training solutions.

5.1.5 Sy stematically evaluate individual and team performance to identify areas for improvement.

5.1.6 hiaintain an awareness of plant modifications and procedure changes.

5.1.7 hiaintain and enhance teamwork and diagnostic skills.

5.1.8 increase the level of understanding of applied fundamentals presented in initial training.

5.1.0 Enhance the professionalism oflicensed personnel.

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 hlanager.

The flexible component, an operational review, will provide a means for updating licensed personnel on changes to procedures, modifications, lessons learned from operatin sexperience, and needs identified from operator feedback and assessments. The content of the flexible comporent will be finalizedjust prior to the training cycle. The short range training plan captures the cycle content and is finalized upon completion of each training cycle.

5.2.1 The tixed and tlexible components of the program constitute a systems approach to training and include dynamic simulator and individual skill evaluations which require licensed personnel to demonstrate competency in selected plant evolutions.

The plant control manipuhtions listed in 10 CFR 55.59 C.3, as well as those addressed under INPO ACAD 86 025, are contained in Appendix A. These manipulations 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 feedbt.ck from operator surveys.

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. <. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Resision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAM 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.

5.2.3 Just in Time Training (JI1T) will run concurrently with, and independent of, the Licensed Operator Requalification Training program. JITT topics will be identified by Operations Management and the Operations Trainir.g Coordinator and may include necessary training for such issues as procedure changes, modification installation, use of temporary equipment, infrequently p erformed tests or evolutions, or items requested by the crew Duty Shift Superintendent.

These topics are very specific and targeted in nature and will be delivered on an as needed basis. The JITT administrator will maintain a log of all JITT "on line" training occurrences.

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 in teams as " mini scenarios."

5.2.5 Operating experience, inch'dmg in house experience, industry experience and/or selected non industry experience, will be evaluated for inclusion in requal training. The Regulatory Services group tracks many types of operating experience and can be used as a tesource w hen researching training topics.

5.3 ' record of program content shall be maintained on file by the Operations Training l up for the previous and current calendar year.

5.4 1 rogram content shall be reviewed and approved annually by the Operations Manager and the Operations Traimng Coordinator and updated accordingly Page 5 of 27

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. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAM 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 six training cycles per year. See Appendix G, Generic Schedule.

< 6.3 Each training cycle will normally be at least six weeks lorg to accommodate each of the six operating crews. If the training cycle does not accommodate a separate training l segment for staff personnel, they will attend required lectures throughout the cycle.

. 7.0 TRAINEE EVALUATlON: INITIAL TRAINING See TRPR 18.0," Control Operator Training Program", or TRPR 19.0, Senior Reactor Operator Training Program".

8.0 TRAINEE EVALUATION: CONTINUING TRAININ.G 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?

8.1.3 On which learning tasks is the trainee progressing satisfactorily?

8.1.4 On which learning tasks does the trainee need help?

-8.1.5 Which trainees are having learning problems that they need remedial work?

8.1.6 _ Which trainees have mastered the teaming tasks to such a degree that they can be considered _ qualified to continue _ performing the functions govemed and by their license independent of direct supervision?

8.2 Segment Evaluations 8.2.1 Evaluatiore., should be in accordance with TIP 8.6, " Written Evaluations" and TIP 8.8," Simulator Traming and Examination",

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• $. NUCLEAR POWER BUSINESS UNIT TRPR 33.0

..TRMNINO PROGRAMS NNSR [

Revision 6

. LICENSED OPERATOR REQUALIFICATION July 15,1997

! -TRAfNING PROGRAM i

8.2.2 Each segment of training will normally be evaluated. The evaluation shall be

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a written evaluation, a performance type evaluation, or a combination of both.-

8.2.3 The number of evaluation mechanisms utilized in a given cycle vill normally '

be limited to two or less. This concept minimizes the stress associated with multiple assessments and maximizes the training time available during the cycle, w

8.2A Enabling learning objectives may be evaluated through written quizzes, graded assignments, self assessment instruments, or oral questioning as

- deemed appropriate.

8.2.5 Unless a lesson in the segment of training is evaluated singly or a performance-type evaluation is administered, a written quiz that cddresses the critical issues covered in that training cycle - - and previous cycles, as appropriate -- will normally be administered.

S.2.6 Specific ski!'s evaluations will be conducted when appropriate to ascertain mastery of a specific skill or evolution that was trained on during that

, segments' training.

8.2.7 Selected cycles will contain a dynamic simulator evaluation. The subject matter of the dynamic evaluation should be independent of the training segment content. Its purpose is to evaluate a crew's performance as a " cold assessment" (i.e., without pc'or training)

Personnel on each crew will be rotated to eqititably evaluate each individual at the various positions on the watch team. The Lead Evaluator will ensure this rotation takes place.

8.2.8 Deticiencies in knowledge or performances identified by the segment evaluation shall be corrected prior to resumption of duties.

Dynamic evaluations may be categorized as "unsat" (one or more critical tasks missed) or " sat" (all critical tasks met). Performance discrepancies are addressed in the scenario critique and/or post-dynamic practice session.

8.2.9 A licensed individual may be exempted from a segment evaluation if he or she developed, reviewed, or approved the evaluation instrument in its entirety.

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,e il . NUCLEAR POWER BUSINESS UNIT TRPR 33.0 '

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TRAINING PROGRAMS NNSR-

- Revision 6

' LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAM h l _ 8.3 Gradine of Evaluationutnd Remediation Reauirements i-8.3.1 In addition to the grading criteria contained in TIP 8,6. " Written Evaluations,"

all subjective type written evaluations (essayahort answer) with a score between 75,0% and 85.0% require " Independent Grading,"

r a. The " independent grader" reviews the evaluation against the KEY and -

independently comes up with a score for each question on the evaluation.

b. This individual will sign tne evaluation cover sheet " independently graded

{ by _ " or with a similar note to doctanent this independent

- grading.

c. The final score for each subjective type question will be lowest of the two scores detennined by the two graders. The overall evaluation score

]- entered into the trainee's record (and used to determine PASS or FAIL)is the sum of each of these " lowest scores" for each question.

[ 8.3.2 Actions that must be taken for any evaluation score of UNSAT or <80%

a. Intbrm individual they are removed from licensed operator watchstanding s

duties until completion of formal remediation.

E

b. Infbrm Operations Manager, Operations Training Coordinator, crew supervision, and the operations group scheduler of the failure and the

} watchstanding restriction.

c. Iland write a note in the Operations Quarterly Status Report identifying temporary removal from watchstanding duties. Inform Operations Information Specialist to update the report.

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. d. Develop remediation for the failure.

l 1. Remediation must address the specifics of the evaluation failure,

2. A brief review of past evaluation results for trends should be conducted and considered in the remediation (a more thorough review would be warranted for a failure of an NRC exam).

3. Rernediation for NRC exams and simulator dynamic exam failures must be followed by a re-examination.

t 4. Remedials are prepared per TIP 8.6 and require discussion / review with the training program administrator and training coordinator.

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. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR ,

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e. Upon satisfactory completion of all remedial action, make sure all of the above individuals are informed of the licensed operator's return to watchstanding duties and that the Operations Quarterly Status Report is  ;

updated, i

8.4 Reauali6 cation Exams 8.4.1 Requalification exams shall be adminiatered 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 written examination based on the 24 month continuous program, and to pass an annual operating test.

8.4.2 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 Firial Safet) Analysis Report, Technical Specifications, system descriptions manuals and operating procedures, facility license and

' license amendments, and licensee event reports.

a. Section A of the examination shall be an open-referenced, static simulator l

" examination focusing on plant and control systems.

b. Section B of the examination shall be an open-referenced examination focusing on procedure limits and administrative controls. It may be administered in the simulator or a classroom.

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NUCLEAR POWER BUSINESS UNIT- TRPR 33.0 .

TRAINING PROGRAMS .NNSR l Revision 6

, LICENSED OPERATOR REQUALIFICATION - July 15,1997 ,

e TRAINING PROGRAM I 8.4.3 A formal sample plan will be produced on a biennial basis in support of the comprehensive requalification written examination. A significant amount of the material contained in the p'an should be assembled on a cyclic basis to maximize efficiency. The sample plan content should contain the following:

a. Cycle Schedules 4

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 i

This section identifies the major categories (topic areas) considered for the i

examination. Applicable training items from the most recent two year i implementation of the licensed operator requalification program should be divided and assembled under the identified topic areas. A summary of each topic area should include:

1. Total hours of training time devoted to the topic area

2.  % of cycle devoted to the topic area L 3.  % of examination devoted to the topic area

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 lirtk and includes the following:

1. Exam item identifier

2. Related objective Page 10 of 27

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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 8.4.4 General Examination Guidelines (Written) i 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 r.n adequate base to determine areas in which retraining is needed to upgrade licensed operator and senior operator knowledge.

d. The examination should be graded as one entity with a minimum score of 30% required for passing,

e. The SRO examination should differ from the RO examination by 215%.

Areas to consider for SRO level questions include, but are not limited to:

1. Technical Specifications and their bases

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 Page !I of 27

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. . NUCLEAR POWER BUSINESS UNIT TRPR 310

- TRAINING PROGRAMS NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 S -

TRAINING PROGRAM y

f. The examination team should consider incorporating 10 to 20%

non requalitication cycle specific examination items.

) g. Individual questions should reference K/A values of 2 3.0. >

h. Versions of the examination will be selected and administered from week

- to week at the discretion of the licensed operator requalification program admin!;trator.

i. 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 avoiding compromise, instructors who are on the examination development team shall wear "NRC Exam Team" identification tags.

4 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 with any examinee until that examinee has completed their examination.

8

k. SRO Certs are exempted from taking the examination if they were on the development team.

1. Remedial 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 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.

8.4.5 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.

8.4.6. General Examination Guidelines (JPM Walk through)

- a. The examination will consist of 5 JPMs.

1. - Three JPMs will be administered in the simulator. The design l should provide for evaluation of a nomial, an abnonnal, and an l emergency task.

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2. Two JPhts 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 JPhis selected for the current examination year should have appeared on the preceding years examination (ex: if 20 JPhis are selected for the current years examination, s4 of those JPhis should have appeared on last year's examination)

c. A minimum of four JPhi examination packages should be developed each year. A comparison of any two packages shall reveal no more than one common JPht,

d. JPNI selection should be based on one or more of the following criteria:

1. Task analysis criticality rating of"3"

2. New or recently moditied system / component

3. Systems that are the subject of recent NRC LERs 4 Systems that aw the subject of recent NRC Information Notices

5. Probabilistic Risk Assessment (PRA) risk dominant systems, components, or events

c. To pass the JPhi walk through examination, each examinee has to successfully complete at least 4 of 5 JPhts. To successfully complete a JPNI, the examinee has to complete all critical steps specified in the JPht.

Critical steps are those which when not performed in proper sequence, not performed at the n oper time, or not performed correctly willprevent the system)Famfunctioning properly or preclude the successful 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 indications that should be readily observed.

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2. Ntaintaining 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. Thi.; will ensure that the evaluator provides timely cues and-detects errors in performance.

4. As an evaluator, questioning the licensee during the performance of an examination JPhl, to gain insight into what the examinee is thinking, is distracting and may result in prompting or leading the candidate. Evaluators may ask the examinee questions clarifying the performance of the JPNI only after the JPNI has been completed.

5. The evaluator should be careful to shield any notes or grading from the examinee to prevent giving the examinee an indication of performance, which may either provide a false sense of security or increase stress levels.

6. When conducting JPhis in the simulator, evaluators should not manipulate any controls or silence alarms associated with the JPht.

This provision does not prohibit evaluators from acknowledging non pertinent alarms or unexpected reactions of other systems not associated with the task being evaluated.-

7. The evaluator should brief the examinees, either individually or as a group, prior to the start of the walk-through examination.

g. Versions of the exar.unation 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 of examinees until those examinees have completed their examination. To aid in avoiding compromise, instructors who are on the examination-development team shall wear "NRC Exam Team" identification tags.

b

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.

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- TRAINING PROGRAM

j. Remedial examinations should be developed as required and should be tailored to the individuals who received the failing yade. The content shall differ from the originally administered examination by 2 50% and should include JPMs that focus on those areas where performance was deemed weak.

8.4.7 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 inodified 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.

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 and Qualitative Scenario Attributes" to ensure consistency in scope, depth, and complexity.

e. Examination package development

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.

2. All scenarios should be pre validated in real time on the simulator Page 15 of 27

, l NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAh1S NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAN1 ts r*m 3.

Crew personnel rotations should be set prior to administering the examination

f. The Operations hianager 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 Alanager or his surrogate having authority for determining the fmal 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.

j. 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 of examinees until there examinees have completed their examination. To aid in avoiding compromise, instructors who are on the examination development team shall wear "NRC Exam Team" identification tags.

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 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 hlanager and Operations Training Coordinator.

8.5 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 recoris.

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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 'he 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 /conditio..s 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 t-evaluation guidance,

d. An individual with en active license who fails a segment evaluation shall not perform licensed duties until remediation has been satisfactorily l completed (see section 8.3.2 for details).

l 9.1.3 The licensee must pass the requalifications exams of Section SA.

a. The written examination passing criterion is 80%.

h The dynamic simulator evaluation passing criterion is " SAT"

c. The JPM passing criterion is 80%.

d. An individual with an active license who fails either the written examination or the opemting test shall not perform licensed duties until remediation has been satisfactorily completed (see Section 8.3.2 for

. details),

e.

Requalification examination failures (written and operating), require reexamination in addition to remediation.

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9.1.4 The licensee shall perform the functions authorized by his/her license on shift for a minimum of seven 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter.

This on shift time shall be documented on PBF-2094,"NRC License: Shills to hiaintain Active Status."

9.1.5 The licensee shall have a medical examination pursuant to 10 CFR 55.21 bienniall> of the anniversary date of the most recent exam. A copy of NRC-396, " Certification of hiedical Examination by Facility Licensee," shall be on file with PBNP Training. hiedical examinations are administratively controlled by NP 1.10.1. "Sledical Certification and Recerd Keeping for 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.

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" I c. Skills evaluation passing criterion is in accordance with the associated evaluation guidance.

9.2.3 The licensee must pass the requalifications exams of Section 5.5.

a. The written examination passing criterion is 80%.

l b. The dynamic simulator evaluation passing criterion is " SAT".

c. The JPNI passing criterion is 80%.

d. . Requalification examination failures (written and operating), require reexamination in addition to remediation.

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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 hiedical Examination by Facility Licensee," shall be on file with PBNP Training, hiedical examinations are administratively controlled by NP 1.10.1, "hledical Certification and Record Keeping for Licensed Personnel."

9.3 Activatine an inactive License 9.3.1 An individual with an inactive CO license may change the license to an active status by completing TRQN! 18.32, " Qualification Card: Inactive License."

Reference 10 CFR 55.53(f). Successful completion of TRQN! !8.32 requires that a licensee certify that his/her qualifications and status of the license are 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 /> (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 of the plant and all required shift tumover procedures.

9.3.2 An individual with an inactive SRO license may change the license to an active status by completing TRQN! 19.32, " Qualification Card: Inactive License." Reference 10 CFR 55.53(f). Successful completion of TRQN! 19.32 requires that a licensee certify that his/her qualifications and status of the license are current and valid and that the license has completed 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (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 of the plant and all required shift turnover procedures.

9.4 Excitation of License 9.4.1 An individual's license shall expire six years after the d:.te of issuance, upon termination of employment with Wisconsin Electric, or upon determination by

- Wisconsin Electric that the individual no longer needs to maintain a license.

9.4.2 Wisconsin Electric shall request the NRC to terminate the license of any i~ndividual who does not continue to meet regulatory requirements.

10.0 PROGRAM EFFECTIVENESS EVALUATIONS /SUPVEILLANCE 10.1 - Training and/or Operations personnel shall perform the following program effectiveness surveillance in accordance with the requirements of the training procedure identified:

10.1.1 Trainee Reactions -- TIP 10.3, Trainee Reaction Forms 10.1.2 hlanager/ Supervisor Observations -- TIP 10.1, Performance Assurance System Administration Page 19 of 27

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-. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAh1S NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAM 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 10.1.6 Training Advisory Committee (TAC) - TRNG 10.0, Management Oversight and Systematic Evaluation.of Training Effectiveness 10.1,7 Simulator Evaluations -- Tl? i.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 effectiveness. These crew training effectiveness reviews are an integral part of assessing program effectiveness, 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, 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 program changes, 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 11.1.2 Ensuring that evaluatic,ns are prepared and administrated as prescribed _.

I1.1.3 Ensuring that program effectiveness surveillances are performed within the frequency prescribed Page 20 of 27

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- TRAINING PROGRAM 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 l the missed training (see Section 13.2). .

f l_ a. Make up training for a simulator class should include simulator time,

b. Make up training for a classroom presentation should include a discussion with the instructor.

c. Each requal lesson should include a make-up contingency describing these requirements.

11.1.5- Ensuring that program completion audits are performed i1.1.6 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.

12.0 MANAGENIENT RESPONSIBILITIES 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 Evaluation of Training Effectiveness," exists to facilitate work group involvement, steering, and oversight of the operator training and qualitication program. The Operations TAC represents a partnership between Operations and PBNP Training, with each partner delivering the considerations enumerated below.

12.1 Or'erations:

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 qualitication process.

12.1.2 Operations management will periodically observe classroom training, simulator training, and on the job training and task performance evaluation

- activities in progress to verify that group and personnel needs are met, performance standards are reinforced, and participants are challenged.

12.1.3 Operations management will periodically observe in plant task performance to

- verify that training is effective.

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-TRAINING PROC RAM 12.1 A Operations management will ensae that personnel attend required training or participate in timely make-up.

12.1.5 Operations management will ensure that trainees conduct themselves in a professional manner.

12.1.6 Operation., management will ensure that the licensed operator requalineation program is carried out in accordance with the provisions of TlP 9.5, "On the Job Training and Task Qualification," and that trainees complete designated training and quali6 cation 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.

, 12.1.8 Operations management will ensure that on-the job training is conducted by qualined 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 quali6ed individuals using valid evaluation methods, that trainee performance is measured against established standards prior to task or job qualification, and that remediation and reevaluation are provided when

• 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 qualiGcation programs, 12.2- Raining 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 qualifications required for their respective positions.

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12.2.2 Training management will maintain an instructional skills training program that develops the necessary instructor capabilities to fulfill training program requirements in all applicable training settings.

12.2.3 Training management will ensure that instructors are provided with adequate time to prepare tc Jeliver effective and consistent training.

12.2.4 Training management will regularly evaluate the instructional skills and

[ evaluation techniques ofinstructors.

12.2.5 Training management will ensure continual instructor development to maintain or improve needed technical and instructional knowledge and skills and to address weaknesses identified 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.

12.2.7 Treining management will ensure that learning objectives are derived from an analysis ofjob performance requirements, that they are used to establish '

i- essential training content, and that they are sequenced to facilitate the progression of training.

12.2.8 Training management will ensure thatjob related knowledge is provided through effective classroom training, laboratory training, simulator training, or self study.

12.2.9 Training management will ensure that self-study and individualized instruction, when used, provide the trainee with sufficient guidance and supporting materials for achieving the learning objectives.

12.2.10 Training management will ensure that lesson plans and other training material used for classroom, laboratory, simulator, self-study, and on the-job training are accurate, support the learning objectives, and promote effective delivery of 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.

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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 i e instructional techniques that promote mastery of the learning object. s and encourage trainee participation.

12.2.14 Training management will provide assistance to and monitoring of subject

matter experts (SMEs) used as instructors to ensure quality training.

b 12.2.15 Training management will maintain training records to support management information needs and to provide required historical data. ,

12.2.16 Training management will maintain a matrix cross referencing tasks to training material to confimi training program content current.

12.2.17 - Training management will write an End-of Cycle Report following each full training cycle and provide results to the Operations Manager.

F 13.0 PARTICIPATION REOUIREMENTS l 13.1 Individuals enrolled in the licensed operator requalification training program shall attend all scheduled classroom and simulator training unless incapacitated by illness or

! specifically excused for some other good cause. Planned absences shall be authorized by i 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

)-

week scheduled shall attend that training in another training week. In the event that this is not possible, the missed training shall be made up in accordance with the lesson plan's l make-up contingencies.

i 4

13.2.1 Trainees should normally complete all make-up training within one cycle following the missed training.

13.2.2 . .After one cycle without completion of all required make-up training, the affected individual shall discuss the reasons behind the delinquency with his supervisor and the Operatons Manager.

l 13.2.3 After two cycles without completion of all required make-up training, the

. affected individual will be removed from watchstanding duties until make up training is completed.

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13.2.4 After three cycles without completion of all required make-up training, the p affected individual will have his license submitted for termination.

i 13.2.5 Personnel with extenuating circumstances (e.g., lost time injury, serious illness) will be evaluated on a case by case basis and may not be subject to the above requirements with the exception that all make-up training be completed

- prior to resumption of watchstanding duties.

13.2.6 The Operations hlanager reserves the authority to exempt an individual, if emergent, in accordance with TIP 9.2, " Training Exemptions."

t 13.2.7 hiake up of continuing training sessions presented during a cycle but outside the scope oflicensed operator required material shall be determined on a case by case basis by the Operations hianager in consultation with Operations -

Training.

, 13.3 in addition to being physically present for scheduled training, licensed operators shall exhibit professionalism by conducting themselves in the following manner:

13.3.1 Being mentally alert, attentive, and ieceptive to the training being provided.

13.3.2 Participating in the training by developing a questioning attitude : hat 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 hiaintaining 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.

= 13.3.6 Accepting personal responsibility for completing all training and a requalification requirements.

13.3.7 Using the time given over to requalitication 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 assess _ ment 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 qualitication requirements.

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14,0-- . REFERENCES F 14.1 Title 10, Code of Federal Regulations, Part 55 14.2 NUREG 1021 Operator Licensing Examiner Standards, Revision 7.

I 4.3 Institute of Nuclear Power Operations,INPO 86 025 (Revision /1, Guidelinesfor Continuing Training ofLicensedPersonnel. Atlanta: Author, l 989.

14.4 . National Academy for Nuclear Training, ACAD 85-006 Principles of Training System

Development. Atlanta

Institute of Nuclear Power Operations,1993.

l 4.5 National Academy for Nuclear Training, ACAD 92-004, GuidelinesJbr the Conduct of Training and Gualification Activities Atlanta: Institute of Nuclear Power Operations, 1992, 14.6 National Academy for Nuclear Training, ACAD 9/ 0/5. 77:e Objectives and Criteriafbr Accreditation of Training in the Nuclear Power Industry, Atlanta: Institute of Nuclear

Power Operations.1991.

14,7 National Academy for Nuclear Training, ACAD 91006. Guidelinesfor On the-Job

, Training md Evaluation. Atlanta: Institute of Nuclear Power Operations,1991.

I4.8 ' National Academy for Nuclear Training, ACAD 9/-0/2, Guidelinesfor Training and-Quahfication ofLicensed Operators, Atlanta: Institute of Nuclear Power Operations, L 1991.

15,0 APPENDICES / ATTACHMENTS 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 Appeudix F, Short Range Training Plan Development Page 26 of 27

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-15.7 . Appendix G, Generic LOR Schedule 15.8 Appendix li, Operationally Significant Administrative Procedures .

15.9 Appendix 1. Synopsis:- Program Revision Record Page 27 of 27

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-TRAINING PROGRAM APPENDIX A PLANT CONTROL MANIPULATIONS FOR CONSIDERATION Code of Federal Reculations 55.59CFR(A) 55.59CFR(1) 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 Dow/ 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) 55.59CFR(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, signincant 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(1l) 55.59CFR(R) loss ofIA mispositioned or dropped rods i

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.g. -

ACAD 86-025

. switch feedwater control from . boron control malfunction . PORV or Safety salve stuck open manual to auto e place into or remove from e premature enticality . ATWS service major components or systems

. inadvertent engineered safety . ' loss of heat sink . natural events (earthquake, features actuation tornado, etc.)

t7

. failure of engineered safety . station blackout . failure of turbine extraction steam feature to actuate non return valves

. RCP trip . failure of containment . isolation . inadsettent main steam or feedwater isolations

. control room evacuation . containment piessure or . failurt af turbine generator temperature high

. RCP seal failure e inadvertent containment isolation . excess feeJw ater transient

. condensate pump or sptem e inadvertent containment spray failure

. generator stator cooling failure . accidental liquid or gaseous release

. loss of annunciator pwr

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' ts APPENDIX B LOR FlXED COMPONENT SUGGESTED TOPIC AREAS (tliese areas re0cct the general requirements of 10 CFR 55.59 as well as the guidance ofINPO 86-025 rev.1 this is not an all inclusive list) 10 CFR 55 50 INPO R6-025 rev 1. cont.

. theory and principles of operation . case studies of operational experience

. general and speede plant operating characteristics e severe accident management

. plant instrumentation and control systems . administrative procedures, conditions and limitations

. plant protection systems . facility design and license changes

. engineered safety systems

. normal, abnormal and emergency operating _ . site emergency plan procedures

. rad:ation control and safety . industrial safety

. technical speci0 cations . EOP and CSP basis steps

. applicable portions of title 10, chapter I, Code of . supervisory skills training Federal Regulations INPO R6-025 rev i

. applied heat transfer, Guid Gow and thermodynamics . teamwork, leadership communications and diagnostics

. features of facility design . major operational evolutions

. plant chemistry control

. fuel handling

. reactor core design parameters and limits

. transient and accident analysis and control, including accident mgt.

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. NUCLEAR POWER BUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 5.1997 TRAINING PROGRAM APPENDIX C LONG RANGE TRAINING PLAN REQUIRED OR COMMITMENT RELATED TOPICS 4 References Freauency Commitment Complete task P7311 AOT, Wear NUREG 0041 Annual SCBA 10 CFR 20.103 Review and update training, as AM 3-1, Corporate Water Chemistry Annual 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 Making Operating Philosophy NUTRK: SOER 94-0104A/l Conduct Operational Examination 10 CFR 55.59 Annual (Dynamics /JPMs)

Conduct Annual Danger Tag NP l.9.15 Annual -

Refresher Training Review key aspects of SOER 96-1 SOER 961 Annual 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 04 All-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 -

plant during each two year operations listing.

training plan-

. Refresher training on PF/JPM - OM 2.14, PF/JPM Administrator Biennial Administrator responsibilities l

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Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAINING PROGRAM APPENDIX D i ATTENDANCE REQUIREMENTS FOR PERSONNEL ENROLLED IN THE LOR PROGRAM (OR APPLICABLE PORTIONS)

SCHEDULED TRAINING Flexible Comnonent Skills Fixed Simulator SRO OE PSU Evaluation Component Dvnamic Licenses

]

Active / Inactive ROs X X X X X SROs X X X X X X

"

• S RO Certitications/t,T_A OPT SRO CERTS X X 'X X STAFF SRO "X X "X CERTS DTA X X X

' Skills max be required by the OPT SRO Certs if an individual administrates P/F, JPM or skill evaluations.

"Mav be required to attend depending on the subject matter. Attendance requirement to be determined ,

by Opera: ions Manager / Operations Training Coordinator.

"* Participation described for program management purposes only.

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+1 APPENDIX E 1

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NUCLEAR POWER DUSINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 6 LICENSED OPERATOR REQUALIFICATION July 15,1997 TRAININO PROGRAM O APPENDIX G GENERIC LOR SCliEDULE Cycle 1 Training Cycle l Cycle 2 Training Cycle with requalification written exam (if administered) l Cycle 3 Training Cycle Cycle 4 Training Cycle l Cycle 5 Training Cycle with operational exam l Cycle 6 Training Cycle

. ,o NUCLEAR POWER 13USINESS UNIT TRPR 33.0 TRAINING PROGRAMS NNSR Revision 6 LICENSED OPERATOR REQUAllFICATION July 15,1997 TRAINING PROGRAM '

APPENDIX 11 OPERATIONALLY SIGNIFICANT ADMINISTRATIVE PROCEDURES Nuclear Organi7ation Manual (NOMt None Administnitive Manual (AMh

-1.

AM 3-3. At Power Primary to Secondary Leakage Monitoring Program Nuclear Power Business Unit Procedures Manual (NP2

1. NP 1.1.4, Procedure Use and Adherence

2. NP 1.2.2 Technical Procedure Classification, Review, and Approval

3. NP 1.2.3, Tempora 2y Changes

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

7. NP 1.6,6. Work Duration Restrictions

8. Nr .v.15, Danger Tag Procedure

9. NP 2.3.3, Work Control Center

10. NP 3.2.2, Primary Water Chemistry Monitoring Program i 1. NP 3.2.3, Secondary Water Chemistry Monitoring Program

12. NP 5.3.7, Operability Determinations

13. NP 7.3.1, Temporary Modifications 14 NP 8.1.1, Work Order Processing

15. NP 10.1.1, TS Equipment OOSNoluntary Entry into an LCO

' t

. . NUCLEAR POWER BUSINESS UNIT TRPR 33.0 t

. TRAINING PROGRAhtS NNSR i Revision 6 '

LICENSED OPERATOR REQUALIFICATION July 15,1997 '

TRAINING PROGRAh!

$ l i APPENDIX H. (cont.) I Ornations Manual f 0Nfk i

1. Oh! 1.1, Conduct of Plant Operations

2. OM 3.7, Emergency Operating Procedures Use and Adherence

3. Oh! 3.12, Control of Equipment and Equipment Status

4. Oh! 3.17, independent Check Guidelines ,

5. Oh! 3.18. Operations Administrative Limits

6. Oh! 3.19, Reactor Coolant System Leakage Determination

7. Oh! 3.20 MOV/AOV Operation and Maintenance Guidelines

8. OM 3.26. Use of Dedicated Operators

9. Oh! 3.27, Control of Fire Protection and Appendix R Safe Shutdown Equipment  ;

10. OM 3.29, Pre Job and Post Job Driefings ,

11. Oh! 4.1.1 Post Trip Review l i 12. Oh! 4,2.2, inservice Tests

13. OM 5.4.1, Operations Group Periodic Testing and Surveillance l 14. Oh! 5.4.4 Control of Posted Plant Information

15. ONI 6.1, Performance Assessment Program

16. DCS Handbook (SRO Only) i i

1 9

I 4

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• i APPENDIX 1 SYNOPSIS: PROGRAh! REVISION RECORD Revision 0: Created a separate program description for LOR. Formatted in response to the INPO PBH.RSAQ21 (Operations ASER conducted December 13 17,1993)

Revision 1: Revised program to reflect improvements related to NRC IR 94 003, PBL 94 0296 and Audit A.P 94 20; additionalimprovements 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 j in selected evolutions, adding guidance for development and conduct oflicense requalification examinations, and adding remediation requirements for cycle eve.luations.

Revision items related to NRC Inspection Report 50 266/95002(DRS);

- 50 301/95002(DRS). (LOR Inspection conducted February 13 17,1995).

Revision 3: Updated program to reflect changes in cunent 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 /clariticatioa 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 danser tag refresher training to Appendix C to meet NP 1.9.15 requirement.

Revision 5: Slade program revision record Appendix 1 and added Appendix H, Operationally Significant Administrative Procedures. Added annual commitment to review aspects of SOER 961 and biennial commitment to conduct PF/JPhi Administrator refresher training.

Revision 6: Added Section 8.3 to describe independent grading of tests with scores between 75% and 85%. Added to Section 13.2 to discuss policy for making up missed training. Deleted special quiz remediation allowance far failures between 70% and 80%. hiinor changes to other sections to reflect current practices, s

1 1

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NUCLl!All POWillt IlUSINiiSS UNIT TIP 8.8

• TRAINING lh1PLlihilINTING PitOCliDUltliS NNSR j Itevision 8 i

' Slh1ULATOR TRAINING AND !!XAh11 NATION August 22.1997  !

i i

l.0 SCOPli l Simulator scenarios will be written for evaluation purposes for licensed operator and duty  ;

technical advisor training programs. TLis procedure provides guidelines for the development.  !

approval, implementation. and maintenance of simulator scenarios and the general ginideline for l the conduct of simulator training.

NOTEt Scenarlos that are uwd only during lesson plan implementation may be in the body of the lesson plan and need not conform to the TIP 8.8 guidelines.

2.0 NITRilllilliS OF A GOOD SCI!NARIO 2.1- Simulator scenarios should incorporate recent plant or industry events. t t

2.2- Simulator scenarios should be relevant to the objectives of the lesson.

i 23 Simulator scenarios should consider simulator fidelity and attempt to be as "real" as ,

simulator fidelity will allow.

2.4 Simulator scenarios should incorporate infrequently performed tasks where possible.  ;

2.5 Simulator scenarios should incorporate planned evoletions.

2.6 Simulator scenarios should be developed around perceived operator weakness and designed to enhance problem solving skills.

2.7 Simulator scenarios should efTect the worst consequence (s) of trainee error.

2.8 Simulator scenarios used for examination purposes should meet the expectations of NURl!G 1021," Operator Licensing lixaminer Standards,"

2.9 - Simulator scenario malfunctions / failures should be timed to provide a reasonable interval for trainee action or response (e.g., taking control of automatic actions, alarm response i book usage and Technical Specifications usage, etc.),

2.10 Simulator scenarios should be pre-run to establish fidelity and realism, and to determine  !

intervention points 2,11 Simulator scenarios should have conditions under which the simulator can be in "RUN" during shift turnover.

Page 1 of 14

_ . - . . _ . - _ . _ ________ _ _ _ i_._

r NUCl.l!All POWillt ilUSINiiSS UNIT TIP 8.8 TitAINING lhiPl.lih11!NTING PitOCl!DUltlis NNSit Itevision 8 Slh1UI.ATOlt TRAINING AND !!XAh11 NATION August 22.1997 j 3.0 DYNANilC Sih1UI.ATolt TilAINING AND I!XAhilNATION SCliNAlt!OS ,

! The following sections should be incorporated into all dynamic simulator evaluations.

!!xamination scenarios should be developed using the NI(C Operator Licensing Examiner Standards for guidance. ,

3.1 Imlructor Summary f

{

l hls section provides an overview of the scenario and should include the sequence and general description of malfunctions and events.

3.2 Simulator Shill.Jutunr1 Suflicient time should be allowed Ihr the operators to walkdown the control boards and to

! feel comfbriable with plant conditions (t>pleally 3 5 minutes). The turnover should be used to provide the crew with a synopsis of plant conditions, work in progress, and any equipment out of service. The turnover should also incorporate difTerences between the plant and the simulator (e.g., h10Ds not done on the simulator but done in the plant.)

3.3 SiuniJator Scenario Set Up i ,

3.3.1 This section pmvides guidance to the simulator operator to ensure the .

simulator and the evaluators are ready fbr the scenario to be conducted.

l 3.3.2 The ibilowing Ibrms are provided to help the simulator operator in setting up the simulator and briefing the operators prior to the simulator scenario. These i forms should be utilized during dynamic examinations and are optional for all

~

other sessions.

a. Simulator Setup Checklist (Tit 8.8.2)

b. Simulator Scenario Briefing Sheet (Tit 8.8.3) 4

. c. Communicator Telephone Log (Tit 8.8A)

d. Simulator Book Preparation Checklist (Tit 8.8.6) 3A Scenario Guids

The main tvdy of the scenario is comprised ofinformation to provide control and timing 4

ofinstructor and trainee actions. The body should be set up sequentially by event and include all applicable simulator endes and major crew response actions.

Cues, initiating conditions, and/or any communicator response guidance shc>uld be included to assist the booth instructor (s).

Page 2 of 14

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~' TRAINING lhtPLEhtENTING PROCEDURES NNSR Revision 8 SihtULATOR TRAINING AND EXAh11 NATION August 22.1997 3.5 Evaluation Guids 3.5.1 Dynamic Evaluations The evaluation guide should be setup sequentially by event and include the major objectives by which the crew will be evaluated. In addition to events, sections should be incorporated for areas such as procedure adherence, event  :

classification and feedback on perfonnance strengths / enhancements.  !

Op. rations management expectations should be incorporated where J

applicable.

3.5.? Dynamic Examinations The evaluation guide should be setup sequentially by event and include the '

major objectives by which the crew will be evaluated. Individual evaluators should document results of the evaluation on fonns TR 8.8.1.a through l TR 8.8.1.f. (as applicable). The lead evaluator will compile the forms and l

document the crew cvaluation summary on form TR 8,8.1.

3.5.3 All critical tasks will be denoted by an "*."

3.5A Guidance concerning conduct of evaluations, grading, and remediation requirements is contained in TRPR 33.0, " Licensed Operator Requalification  ;

Training Program" and Section 8.0 of this procedure.

3.6 Qitica! Tasks This section provides a list of scenario critical tasks. Incorrect perfonnance or oraission l of a critical task is the basis for a 6.ew failure on the scenario.

17 Control Room Summary Sheets A copy of the chemistry information normally available in the control room should be nmde available during the dynamic scenario. For IC sets other than IC 1, the chemistry sheets should be included in the scenario package.

3.8 Simulator Scenario Videotaoing Simulator sessions may be videotaped under the following guidelines.

3.8.1 All participants are informed that videotaping will be used.'

Page 3 of 14

l

' NUCl.IIAR POWi!R llUSIN!!SS UNIT

'llP 8 8 C TRAINING IMPI.IIMl!NilNG PROCl!DURl!S NNSR ,

Revision 8 l SIMULATOR TRAINING AND !!XAMINATION August 22,1997  ;

3.8.2 The videotape will be viewed by the participants and management / training people only tbr feedback to the panicipants, unless each partleipant agrees that  ;

the videotape can be saved for training purposes. l 3.8.3 The videotape should be erased after viewing by the participants, unless the participants all agree that it can be viewed by others.

4.0 STATIC SIMUL ATOR SCl!NARIOS ,

The following sections shall be included in all static simulator scenarios. Statie simulator scenarios and questions should be developed utilizing the NRC operator examiner standard for guidance.

4.1 Instructor _ Reference This section provides the instructor with the simulator input information and sequence, the time the simulation is frozen and the active commands.

It should also include training parameters to verify that the simulation was frozen at the appropriate time. These parameters must be checked within the specilled limiis to ensure that the questions associated with the scenario are valid.

4.2 Student Reference Pagg The student reference page should include:

4.2.1 Plant history prior to the initiation event a brief description of the recent '

plant operating history.

4.2.2 - Initiating event - a brief description of the initiating event.

4.2.3 Operator action taken - a brief description of any operator action taken prior to freezing the simulation. ,

4.2.4 Procedure and step in effect plant procedure and step in effect when the simulation was frozen.

5.0 - SIMUL.ATDR SCI!NARIO REVIEW / APPROVAL S Reviews and approvals will be documented on Tit 8.8.5 " Simulator Scenario Cover Sheet" or an equivalenti

-5.1- Author:__ (Required)-

Page 4 of 14  :

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'. NUCl.IIAll POWillt ilUSIN!!SS UNIT TIP 8.8 o TilAINING lh1PLl!Ml!NTING PitOCIIDUltliS NNSit Revision 8 SIMUL ATOlt TRAINING AND liXAh11 NATION August 22.1997 5.2 Technical iteview: (Optional) . Should be obtained for all itevision 0 scenarios. This resiew is not required if the author holds a current Sito certification.

5.3 Group licad: (Optional)(Not required for static scenarios) . Should be obtained for all itevision 0 scenarios, or any scenarios which define personnel responses which are not  ;

defined by procedure. ,

l 5A Training Coordinator: (Itequired)- Denote approval of simulator scenario. ,

The effective date of the scenario is the date on which it is signed by the Training Coordinator.

6.0 0ENiilt AL Sih1UI ATOlt CONDl!CT The simulator is to be utilized like the real plant. All plant procedures, including conduct of operations, should be adhered to. Miscellaneous information used for operator aid should be consistent with the Control lloom.

6.1 The arbitrary operation of any plant system or component is not allowed.

6.2 Simulator controls such as freeze buttons, system shutdown buttons and the instructor console shall be operated only by qualified trainers designated as simulator operator or simulator trainer.

63 When training is in progress, access to the simulator control room will be restricted to involved trainees and trainers. Observers may use the instructors' booth for observation.

lisceptions must be approved by the lead instructor or the Operations Training Coordinator.

6.4 Training department management and operations line management may access training at l

all times.

7.0 CONDUCT OF SIMUL. ATOR Tit AINING SESSIONS 7.1- Simulator Training Schedule The simulator training schedule is maintained by the Training department. The Operations crews should be trained together when practical with a separate session for the licensed non shift staff.

Page 5 of 14

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l 4 '. NUCLliAlt POWillt ilUSINI!SS UNIT TIP 8.8 l

.. 'l RAINING IMPl liMl!NTING PROCl!DUltl!S . NNSit Itevision 8  !

- SIMUI.ATolt TRAINING AND EXAMINATION August 22.1997 l 7.2 Selection of Training The Operations manager and the Operations training coordinator should detennine the I

simulator training to be conducted. Inputs to this determination will include. ,

l 7.2.1 NUTI(K items [

t I 7.2.2 Llilts and Plant Operating lixperience 1(eports.  !

9 I

4 7 2.3 Sol!Rs.

7.2.4 Operator performance on the simulator based on conunon trainee errors and performance evaluations.

7.2.5 Reactivity / control manipulations.

4 4 7.2.6 Plant modifications and procedure changes.

L 7.2.7 Deliciencies on annual requal exams based on examination results.

7.2.8 input from the Operations Training Advisory Committee.

l 7.2.9 Operator feedback 7.3 Conduct of Simulator Trainine i-7.3.1 Ihe attitude and professional demeanor of trainees and instructors should

. reflect the expected control room atmosphere in the plant.' A failure to

reinthree realism during simulator training may result in the trainee developing improper operating practices.

2

• The conduct of simulator training will vary depending on the kind of training to be conducted. Consequently, the training should he designed l and conducted to meet the training needs of the individuals and the team. ,

7.3.2 Continuing training simulator scenarios should address all areas oflicensed operator performance at a frequency sullicient to verify that necessary skills  ;

are maintained. This will be determined annually by the Operations training coordinator and Operations manager.

f-Page 6 of 14 L

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7.3.3 The degree ofinstructor interaction with the trainees should vary depending on the type of training conducted. During initial training, instructor  ;

I involvement should be high, demanstrating and coaching proper perfbrmance and correcting improper perfonnance. During later stages ofinitial training or

. during continuing training, the amount ofinstructor involvement should generally decrease to allow the students to demonstrate their abilities to conduct the evolutions. New evolutions or evolutions that require the use of i new procedures, new or modified equipment, or new systems are generally best presented by using the demonstration method first, followed by instructor facilitated practice, and finally evaluation.

2 7.3.4 Prior to presentation the instructor should assemble and review the lesson i

plan. Preparation should include the following activities:

' a. Review references and procedures that will be used during the exercise to verify that revisions to these documents are incorporated into the training. ,

(This also provides an opportunity to refresh the instructor's understanding of these documents.)

b. Verify the lesson plan has oeen updated to incorporate all change actions issued since last used (e.g., design changes, procedure changes, operating experiences.)

c. Review the learning objectives and detennine how these learning ,

objectives are achieved by the scenario,

d. Verify that scenario initial conditions and malfunctions are still oppropriate Ihr the exercise.

e. It is helpful to discuss the upcoming training with the duty shift superintendent of that crew to identify weak areas on which to lheus during training, f, llave the DSS assign students to job positions based on their individual and group training needs.

g. Prepare for the discussions, demonstrations, or role playing noted in the instructor activity section of the exercise guide.

h. Ascertain the training desires of plant line management, if feasible,

i. Ascertain previous student perfbrmance from inaructors, training management and identify specialized training needs fbr the team or -

specific individual, page 7 of 14

NUCl.IIAR POWiiR llUSIN!!SS UNIT TIP 8.8 TRAINING IMPl.liMl!NTING PROCl!DURliS NNSR I Revision 8 SIMUL.ATOR TRAINING AND I?XAMINATION August 22.1997 l l

j. Practice me scenario on the simulator. if feasible, to be thoroughly familiar with plant response and required actions.  !

7.3.5 Any associated classroom training should be structured to directly support simulator training.

]

7.3.6 During the conduct of training the fbilowing items should be considered:

4 i a. The student's basic knowledge and skills needed to achieve nonnal '

operating activities should be developed belbre off nonnal events and crolutions are introduced as exercises. Proper sequencing oflearning J

objectives within a training program helps to develop this (bundation.

b. During training and evaluation sessions, areas where improvement is needed should be documented and feedback provided to the Operations training coordinator for use in developing future training.

c. T aining should be allowed to progress to the point that either the training objective is achieved or the students are unable to diagnose and respond effectively to the scenario. Care should be taken not to frustrate the students so their perfonnance is affected on subsequent exercises. At that time, the instructor should freeze the simulator and facilitate a critique of student peribrmance or clarify the situation causing the confusion.

Immediate feedback is effective because the students' actions are fresh in their minds, and they can use the critique to improve future performance.

7.3.7 Training should be conducted using a shift team concept. On a routine basis, students should be assigned to the same control room positions that they are

! assigned to in the plant. The procedure describing conduct of operations should be used to define individual team member areas of responsibility. This method of training develops the students' proficiency in their nonnal positions, provides an understanding of the roles of others on the team, and helps develop the ability of the team to work cohesively in diagnosing and correcting operational problems. The duty technical advisor should be periodically included in this training.

7.3.8 During team training, the instructor should observe and evaluate the ,

leadership and supervisory skills of senior control room operators and shift supervisors as well as the communications, technical, and diagnostic skills of personnel perfonning in each control roem team position.

Page 8 of 14

a . NUCl. liar POWER llUSINESS UNIT TIP 8.8

- TitAINING lh1Pl.lih1ENTING PROCliDURiiS NNSR Revision 8 Sih1UI.ATOR TRAINING AND EXAh11 NATION August 22,1997 1

7.3.9 Simulator training in teamwork, diagt.astics, procedures and problem solving should be structured to develop and enhance the ability of the control room team to respond to all plant conditions and result in improved operator performance in the following areas: j

a. Ability to use symptom based emergency procedures through a better l understanding of the technical bases and intent of those procedures, as )

well as an improved ability to think logically while using those 1

procedures. ,

i

b. Ability to predict plant response and the effects of operator actions.  :

c, Ability to think through changing conditions logically, thus increasing the possibility of terminating the event and initiating appropriate recovery actions,

d. Ability to focus on critical safety functions.

e. Ability to cope with situations not specifically addressed by procedures or beyond the conditions assumed in procedures.

- 7.3.10 To facilitate an effective critique, simulator instructors should use good monitoring techniques and accurate written notes of demonstrated skill and knowledge weaknesses.

7.3.11 The critique should consider the following:

a. Reinforcing skills and knowledge gained during training,

b. Recognizing progress and good perfomiance.

c. Reinforcing a conservative approach to reactor safety. (GJh1 commandments of reactor safety)

d. Identifying student and team performance weaknesses and providing guidance or training to correct these weaknesses.

c. Correcting student misconceptions,

f. Reviewing the accomplichment of position specific objectives.

g. Evaluating problem solving techniques.

h. Reviewing the training.

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• TitAINING lh1Pl.lihil?N' LING PROCl!!)Ulti!S NNSR llevision 8 SihtUI.NIOR TitAINING AND liXAh11 NATION August 22.1997

i. lleviewing questions asked during the training.

J. Soliciting student questions and discussion of correct answers.

k. Identifying needed procedure improvements.

1. Identifying needed plant policy clarification,

m. Identifying needed simulator improvements.

7.3.12 The demonstration moJe of training should normally be used any time the skills and knowledge required to perfbrm specific tasks are new or significantly modified from previous experience (e.g., initial training).

Otherwise, a guided problem solving discovery method should be employed to enhance learning. The fbilowing are some of the situations for which demonstration training is effective:

a. Reinforcing classroom sessions in theory or system operation.

b. Creating awareness oflessons learned from plant and industry operating experience.

c. Demonstrating the effect operators or other personnel have on the plant w hile performing theirjobs.

d. Demonstrating the skills required to control the plant (e.g. maintain steam generator levels with manual feedwater control or synchronize the diesel generator.)

e. Demonstrating the effects of a transient on the plant.

f. Demonstrating the effective use of plant procedures to mitigate the j severity of an event,

g. 1)emonstrating good operating practices and watchstanding,

h. A classroom preview prior to the simulator session can maximize the use of simulator time and can be used to review the following:

l. The learning objectives for the demonstration.

2. Recall of prior, relevant learning.

3. Fundamentals and principles to be demonstrated.

Page 10 of 14 C

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4,  !!xpected plant or system response. 4

5. Relationship of the demonstration to thejob of the student.

6. hiajor controls and indications that will be used.

7. Relationship of the demonstration to plant or industry operating experiences.

8. Procedural strategies that will be used to mitigate the consequence of or terminate the event. l

9. Problem solving techniques.

8.0 FVAl>UNIION OF TRAINiiliS 8.1 livaluations of the crew should be performed several times during the year by representatives from the Training department, plant management and the Operations manager or an approved designee. These evaluations are used as a periodic checkpoint of the crews performance, teamwork, and communication skills, livaluations will also be performed on an annual basis in conjunction with the annual operational examination.

The Operations manager or an approved designee should be a member of each evaluation team. Failure of a simulator perfonnance evaluation shall result in remediation as .

determined by the Operations training coordinator and Operations manager. livaluation

<eenarios given between annual exams should enhance the crews' problem solving skills.

Problem solving is initiated only in unique situations. Scenarios then should contain elements that challenge the crew to evoke problem solving techniques, and part of the evaluation should feed back to the crew how its problem solving skills were executed or could be enhanced.

8.2 Some methods to guide problem solving include:

8.3 Forcing the crew outside existing procedures by:

8.3.1 Failing of equipment relied upon to mitigate the event.

8.3.2 Going beyond the procedure assumptions.

8.4 Creating complex diagnostic scenarios by:

8.4.1 Failing indicators relied upon to diagnose the event.

8.4.2 Creating multiple failures or subsequent, related or unrelated failure events.

Page 11 of 14

• NUCl.liAlt POWi!!(llUSIN!!SS UNI 1 ~11P8,8

. 11(AINING lhil't.lihil!NTING PI(OClii)Ultlis NNSit itevision 8 Slh1UI.ATOltTi(AINING ANI)liXAh11 NATION August 22,1997 8.5 Training scenarios must create an emironment for continued improvement. Continued improvement is defined by the retention and practice of existing skills combined with the acquisition of new skills, lloth are enhanced by the problem solving process. Old skills are recalled to achieve new ones through the problem solving process.

H6 1 he irwmnil!111 tin of the lead evaluator, simulator booth operator and communicator are located in Appendix A. "lixpectations for 1. cad livaluators, llooth Operators and Communicators."

9.0 1(lil:lil(l!NCl!S 9.1 NURiiG 1021," Operator 1.icensing lixaminer Standards"

- 9.2 ACAl) 90 022," Guidelines lbr Simulator Training" 93 INI'O 86 025," Guideline Ibr Continuing Training of1.icensed Personnel"

(

Page 12 of 14

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ ____A__----__--__.i.__1.___.m_w..-__m.m _.-_ _ _ _ _ ____..

• NUCLl! Alt POWIIIt ilUSINilSS UNIT Til' H,8 TI(AINING lhiPl.lihil!NTING Pl(OCl!DUltliS NNSit Ibwision 8 Sih1ULATolt TithlNING AND liXAh11 NATION August 22,1997 APPL!NDIX A I!XPl!CTATIONS l'Olt 1.l!AD liVALUATollS,1100111 OPlil(ATOLLS, i AND CohthiUNICNIOllS LIIAD liVALUNIOlt 1:Olt DYNAN11CS

1. Iteview the crews previous dynamic quiz noting strengths, areas needing improvement, and !!OP implementation and/or action dilliculties.  !

l 2. Iteview the crew lineup sheet from previous scenarios to ensure that each licensed operator is rotated into every position he is qualified for.

Develop the dynamic to be utillied for the quix.

) 3.

4. hiake three copies of the scenario one for the booth operator, one fbr the lead evaluator, and one fbr the conununicator.

5. hiake suflicient copies of the evaluation guide for the evaluators.

6, Schedule and meet with the evaluation team and booth operators at least 15 minutes prior to scenario and then:

, a. Itecord evaluator assignments,

b. Overview the scenario, critical tasks, and endpoint l

7. l'ill out Page 2 of Tit-8.83, evaluating the impact on this scenario,if any.

l 8. When the booth operator is ready and evaluators are briefed, have the crew brought to the simulator.

9 I'rovide the crew with a shill turnover for the chosen scenario. Inform the crew that they have the watch and allow 3 5 minutes for a control board walkdown.

10. ~ Perfonn the simulator observation,

11. Aller checking with all evaluators arut dynamic has reached the end point, infbrm the booth operator to freeze the simulator and infonn the crew the observation is concluded.

12. llave the crew take a break, then perform a self-evaluation, using a blank evaluation guide.

13. Conduct an evaluator critique and record the results.

Page 13 of 14

l NUCl. liar POWIIR llUSINI;SS UNIT llP N.8 j I RAINING lhiPl.lih11!NTING PROCl!DURl!S NNSR l Revisior. 8 l Sih1UI.A' LOR 11tAINING AND liXAh11 NATION August 22.1997 l APPliNDlX A FXPl!CTATIONS FOR Ll!AD liVALUATORS,1100T11 OPl!RATORS, AND COhih1UNICATORS

14. llave the DSS rneet with the lead evaluator and review the results. When the DSS is satisfied with the content / focus of the summary, rejoin the crew.

15. llave the DSS conduct a critique with his crew, facilitating as required and reinforcing evaluator observed items that were not covered during the self critique.

16. hiale a copy of the evaluation for records to be sent with the attendance sheet, place the original crew evaluation in the crews binder, and write the crew lineup on the crew lineup sheet.

1 I 1100T11 OPl!RATOR I OR DYNAhtlCS

! l. Set up the simuhitor in accordance with TR 8.8.2 at least 15 minutes prior to evaluation.

2. Operate the simulator per the lead evaluator's direction.

3. When the dynamic is concluded, remove any material associated with the dynamie, and store / dispose ofit as appropriate.

COhth1UNICATOR FOR DYNAhilCS t

1. Attend the evaluator dynamic briefing (optional).

. 2. Inform the DSS to bring the crew to the simulator per the lead evaluators direction.

3. Foilow the conununicatians standard guideline.

4. Role play as appropriate for the scenario.

5. Act as the security guard when event atifications are required.

6. At the dynamic conclusion deliver the telephone log to the lead evaluator.

Page 14 of 14

+

. DYNASilC EVAL UATION SUSISI ARY SilEET i

Crews Da'e: l SES#/REV: )

Crew Stember l'osition l l'erformance Rating l Evaluator l f f

DSS l l l l

DOS l l l os I I I COI l l l 3rd License l l l l CO2 l l l j DTA 4 Conununicator l Ilooth Operator

) -

lead livaluator I CRiiW l'liiti:ORhl ANCl! RATING (circle one): SAT UNSAT

\

)

. OVERAl.L STRENGTilS i

~

l. ..

l 1

OVERAl.1, AREAS NEEDING ISIPROVESlENT I

t i

i

(

)

l TR-8.8.1 l' age 1 i-- - - _ l

. 0 e

l ( lti.W ( ltl'I IQt:1.(liff Kt.1%i l lINI.NI#1 l 4

4

+

INI.N'l N2: 4

+

+

4 INI.N I W.):

4

=

4 1

INI'.N I N l:

4 Tit.8.8.1 l' age 2

. _ _ . . - . - - . - . - - . - . - . _ . . ~ - - - -

- _ _ = ~ - .

- a o, e l'.VI.N I 05: l 4  :

+

+

1 I:VI.N I #6:

+

+

+

+

4 k

i T

Gl:NI, HIC OM 1.Xi'Iri A IIONS /1: l't. ant e i +

4 4

4

'l I:AM $ Kit.l.h:(communications, tram buildme, conflict resolution, crew brichl 1

4 t

t TR.8.8.1 Page 3

• l'OST lWNAMIC SESSION IN A1.ti A I It)N I 1. A M IDl;N I il ll.D l'It AC i 101, I I l.31%

Citi.W IDl; Nill 11 D 14tACilCl;lil'M5 IWNAMIC CLOSI:OllT:

- Crew facilitatise critique completed per 051 espectations

- Abose identined items resoh ed via discussion and simulator practice *

- Senior evaluation team representath e concurrer.ce on completion of the abos e items 1.liAD I! val UA 1Olt: DATli; nnt I)ynamicpractice sessions are only requiredfor scenarios where olerved we aAneues warrant follow up practice on the simulator 2

TR 8,8.1 .l' age 4

, .. - _ . - _ _ _ . ~ . - . _ _ _ _ . . . . _ - . - . - - . . _ - - - - . - - - - - - . - -

4 Name: St S# Date; ___

laaluator:

DOS COMI'l"I t'.NCll'S .

l Competencpractors 1 2 3 4 5 l

Unsat Marginal Satisfactory Strong Very Strong Diagnosis of 1:s ents and Conditions:

. Itecogniicd off nonnat trends

. Used Ic ference material to aid in diagnosis

. Diagnosis based on multiple indications Understanding of l'lant/ Systems Response:  ;

. l.ocatcJ and interpreted indicators efliciently

. Understood operation of the plant

. Understood setpoints, interlocks, automatic actions Adherenec/Use of l'rocedures:

. Referred to appropriate procedures

. Correctly implemented procedures

. Recognited I:Op entry conditions

. Demonstrated cf ficient use of board operators Crew Operations:

. Communications clear, concise, and relevant

. Crew briefs kept all team members up to date

. Team approach for problem sohing utilized

- Solicited information' assistance from the team Super bor) l'attor:

. Set clear goah, managed stress, resoh ed conflicts

. I'ros ided guidance' assistance as appropriate

. Maintained command and control 1:s atuator Comments b

. I s aluators must be objectne and use factual information to make competency rating detemunations Che6L the column that best dewribes performance for cash fastor

- In cakulaimg a competency ratmg, consider the following guidance Alan) strengths with no or minor weaknesses are typicaH3 considered to rc0cet strong perh<marwe A few strengths coupled with bescrat weaknesses that are relain cl> insignifkant from a safel) standpoint rcueets sausfactory performance hiany weaknesses or signiikant weaknesses are condJered to reDeet marginal or unsatisfactor) perfaimance

. If perfonnansc is linsat, formal remediation is required Tit-8.8.1.a Page1

Name; _ ,_ _ ..

SI.Sn/Date:

livaluator:

DNS COMPLIENCIES Competenc) Tactors 1 2 3 4 5 Unsat Marginal Satisfactory Strong Very Strong i

Diagnosis of 1:s ents and Conditions:

l(ecognlied oft normal trends Used reference material to aid in d;agnosu Diagnosis based on multiple indications Understandingof Plant /Splems Iksponse:

located and interpreted indicators efficiently

-l'nderstood operation of the plant

- Understood setpoints, interlocks, automatic actions Adherence /Use of Proerdures:

I nsured appropriate procedures implemented Correctly implemented E plan Correctly identific J applicable l ech Specs Crew Operations:

Communications clear, concise, and reles ant Crew briefs kept all team members up to date Team approach for problem solsing utili/cd Solicited information auistance frern the team Supersisory I' actor:

Set clear goals, managed stress, resalsed conflicts l'rosided guidance'auistance as appropriate Maintained command and control I:s aluator Com ments

- I s atuators must be obiecin e and use factual it. formation to make competency ratirig determinations Check the column that best describes performance for cach factor

- in cateulating a competene) rating _ consider the following guidance M.tn> strengths with no or rnmor weaknewes are typically considered to set 1nt strong performanet A tcw strengths coupled with sescral weaknewes that are relatncl3 nsignificant i trom a safety standpomt redeets satisfactory performance. Man) weaknewes or significant wcaLnewes are considered to reticet margmal or unsatisfactory performance

- If performance is Unsat, formal remediation i: required

'l R 8.8.1.b Page1

- . = _ - _

=-

t i

Name- St.se Date:

1.s aluator:

UNil' _ CO COM Pl.l f.NCll:N Competencpi'ac tors l 2 3 4 5 Unsat Marginal Satisfactory Strong Very Strong Diagnosis of I:s ents and Conditioni:

Rec ognited ofI-normal trends Used reference material to aid in diagnosis Diagnosis based on multiple indications Understanding of Plant /$ 3stems itesponse:

laated and interpreted indicators cificiently Understood operation of plant Understood setpoints, interlocks, automatic actions Adherence /Use of I'rocedures:

- l(cferred to appropriate procedures Correctly implemented procedures Recognited 1 OP entry conditions Control floard Optrations:

Inated controh efikiently at;d accurately Manipulated controls accurately Compensated f or inalfunctions of equipment Crew Operations:

Communications clear, concise and relesant Crew briefs kept all team members up to date

- Team approach for problem sohing utthred Sohcited information' assistance from the team 1:5 aluutor Comments

- I s alaators must be obi ectn c and use factual inforniation to make mmpetene) ratmg determinanons Check the column that best describes performance for cash factor

- In cakulahng a wmpetene) rating, mnuder the lollowing guidan.c. Stan) strengths with no or sninor weaknesses are ty pically conudered to reflect strong petformance A lew strengths coupled with scscrat weaknesws that are relatncly inupmfkant from a safet) standromt rcDesa utnfactory pertornuuwe Ntan) weaknesws or signi6 cant weaknewes are conddercJ to rcDest marginal or unutnf actory performance

. If performance n t'nsat. formal remedinuon k icquired TR 8 81.c Page1

Name: _ . . _

5t.Sa Date: __

Evaluator: _ _. _

tri A compt:TI:NCl1;S Competency l actors i 2 3 4 5 Unsat Marginal Satisfactory Strong Very Strong Diagnosis of 1:s ents and Conditions

. Recognized ofI. normal trends

. thed reference material to aid in diagnosis Diagnosis based on multiple indications Understanding of I'lant/ Systems Response:

1.ocated and interpreted indicators et0ciently

. Understood operation of plant Understood setpoints, interlocks, automatic actions Adherence /Use of l'rocedures:

. Aucued recusery using 1.Op netaork flowchart

. Anisted crew in interpreting procedural' step intent

. Anisted DSS with impleinentation of 1; plan Assisted DSS with Tech Spec interpretations

. performed NRC noti 0 cations (30 minute goal)

Critical Safety l' unctions:

. Monitored and keep ciew informed of CSI' status Completed ops.79s within time requirements 1:nsured proper transitions to applicable CSPs Crew Operutions:

. Communications clear, concise, and relevant Crew briefs kept all team members up to date

. ~leam approach for problem sobing utilized Solicited information'auktance from the team Es aluator Comments

- i s atuators must tic otycetne and use lastualintorniationi to enaks cornpcterie) rating determistations c heck the column that best describes perfonnatwc for cash factor

. In calculatmg a competene) ratmg,(onsider the following guidanec Many strengths with no or minar weaknesses are 13pically considereJ to reticet strong pertwmance A few s.rcngths coupicJ with sesetal weaknesses that are relatncl> insigmfkant t. a safety standpomt rc0cets sathfai tory performance Many weaknesses or sigmfkant wcakncues arc considercd to redest marymal or unsatistaaory performance

. If performance h Unsat. formal remcdiation u requarcJ Tit.8.8.1.d l' age 1

- _ _ = __

t Name: St.5# Date:

1: valuator: __ ,

ON COMPI:TI:NCil:S Competency,i actors 1 2 3 4 5 Unsat Marginal Satisfactory Strong Very Strong Diagnosis of 1: gents and Conditionst

. Recognized oft nonnat trends

- Used reference material to aid in diagnosis Diagnosis based on multiple indications Understanding of Plant /S3 stems Responset 1.ocated and interpreted indicators ef 0ciently Understood operation of the plant Undert,tood setpoints, interlocks, automatic actions Adherence /Use of Procedures:

Referred to appropriate procedures Correctly implemented procedures

. Recognited 1 OP entry c onditions Demonstrated et0cient use of board operators krtw Operations:

Communkations clear, conciw, and relevant Crew briefs kept all team members up to date Team approach for problem soh ing utilized Solicited information auistance from the team Supenitory I' actor:

Set clear goals, managed stress, resoh ed con 0icts Ptos ided guidance /auistance as appropriate Maintained command and control I s atuator Comments

- I s aluators must tie ob)cetnc and uw factual information to make competene) rating determmatiorn Check the column that best desenbes performance for cash f actor

- In calculaung a competency ratmg. comider the following guidance hian) strengths with no or mmet o aLnesses are t)pically considered to reflect strong performance A few strengths coupled wuh scscral weakncues that arc relatiscl> imignitkarit from a safety standpoint rcilects satnfator) performange, hian) weakncues or signifkant weaknencs are comidered to rcDcet marginal or unsatufador) performanec

- If performan,c is t%at. formal remediation a requi.ed TR-8.8.1.e Pagei

_ _ _ _ . - _ _  :=.__ _

--__ ____m-_ _ - . _ _ _-_.---.__--..-.-__.-_a__

Name: SESa/Date:

E5 aluator:

3rd LICENSE COMPETENCIES Competency / Factors i 2 3 4 5 Unsat Marginal Sati factory Strong Very Strong yg b Diagnosis of Esents and Cor.ditions:

- Recognized off normal trends Used reference material to aid in diagnosis Diagnosis based on multiple indications

- Unde rs tarm.s , 7 8'lant/S) stems Response:

Located and ina 'neted indicators ef0ciently Understood operation et plant

- Understood setpoims, mterlocks, automatic actions Adherence /Us of Procedures:

Refe red to appropriate procedures Correctly implemented procedures

- Reevgnized EOP entry conditions Control Bourd Operations:

l.ocated controls efGeiently and accurately

- Maaipulated controls accerately

- Compensa'ed for malfunctions of equipment Crew Optrations:

- Communications clear, concise, and reles ant Crew briefs kept all team members up to date Team approach for problem solving utilized

- Solicited informati.n' assistance from the team -

Es aluator Comments II _

ll

- I s aluators net be obicetn e and use factual infiirmation to make competene) ratlng detenninat'ons

. Check the column that best describes performance for caeh factor

- In caleutatmg a competency ratimt. consider the following guidanec. Ntany strengths with ,a or minor weaknesses are typically considered to retkct strong performaace. A fe,. atrengths coupled with seseral weaknesses that are relatisely insignificant trum a safety standpoint reflects sausfactory perte mance. Ntan) weaknesses or sigmficant weaknesses are considered to reflect marginal or unsatisfactors performance

- If performance is Unsat, format a: mediation is reqmred TR-8,8.1.f Page1 l 1

SIMUL,ATOlt SETUP CllECKl lST Tile FOLLOWING ITEMS SilOULD llE CllECKED PRIOR TO PERI ORMING SIMULATOR TRAINING OR EXAMINATION:

• Training / examination signs installed Chains installed

• Step counters reset s

) P/A reading correctly Printer on, printer paper loaded, old pnr. touts removed ,

l

}

Pens / charts working properly Replace burned out light bulbs as appropriate

• All magnetic mimic bus positions in proper position (CVCS, SI, elect)

}

Si pump relay removed (when required)

ASIP plasma aligned to appropriate unit PPCS alanus cleared, as able f- _

Purge valves red tagged out Control board recorders aligned / speed appropriately

[l J~

• Main control board and instrument rack doors shut, interior lights off Flags reset CO2 (back)

• Status boards updated Digital display set as appropriate

• All books in appiopriate places i

• RMS grid sheets in place DTA status sheets available llorrs on

• Instrument noise on

• Sim 20 lighting breakers closed

• RMS system paper available (if RMS LCD screen is displayin;,11111111, cycle the toggle switch on the west side of the printer)

• Video tapes available Radios / headsets operable

• Minimum requirement for training TR-8.8.2 Page1

SIMOLNIOR SCENARIO IIRIEFING SilEET 4 - (To be read to the Crew prior to performing a Shif) Turnover)

1. - The primary responsibility is to operate the simulator as ifit were toe actual plant. If a crew member considers that the simulator is not properly responding, the crew member shall mae

decisions and recommendations based on the indications available, 5 2. . Teamwork and communications between operators is evaluated. It benefits the examination rocess to verbalize observations, analyses, and reasons for actions as should be done during actual plant operations.

3. If an operator recognizes but fails to coacct an erroneous decision, response, answer, analpis, action taken, or interpretation made by the operating crew. then the evaluator will assume that the operator agrees with the incorrect item. <

4. A rough log may be kept during each exercise that would be sufTicient to complete the necessary formal log entries.

5. Designated communicators will act as Auxiliary Operators, ilPTs, RCTs, maintenance, plant management, and anyone else needed outside the Control Room.

6. Control board switches may be purposely misaligned to enhance a simulated scenario or transient where appropriate and is not part of the evaluation. If misaligned, they will be tagged out or otherwise noted during the shill tumover. The evaluators will NOT misalign switches during the scenario.

i

'7. -A shift turnover will be provided before the scenario begins. The shift turnover willinclude

- present plant conditions, power history, equipment out of service, cbnormal conditions, surveillances due, and instructions for the shill.-

e

'*8. The crew will be allowed 3 to 5 minutes to familiarize themselves with the status / conditions of the control boards prior to the start of the scenario.

0. - - Are there any questions concerning the administration of the scenario? (Questions should be answered prior to the start of the scenario )

4 d

TR-8'.8.3 ' LPage1 -

f

, -,e , .,-r- _ ,e.. . . , . . . . - - , - - -

(To be identified and explained to the crew by Simulator Operator prior to completing Shift Turnover.)

• The following discrepancies exist between the simulator and actual plant:

. l .-

2.

3.:

4.

- S.:

6.

7.

8.

9.

10.

TR-8.8.3 Page 2

COMMUNICATOR TElliPilONE I.OG Person Reply Reply Time . Contacted Message Req'd. Time

/

TR-8.8.4 Page1

,-, 4 POINT BEACil NUCLEAR PLANT SIMULATOR SCENARIO COVER SilEET i

l PROGRAM:

SCENARIO NUMBER:

SCENARIO TITLE:

Revision: Date:

. Describe changes (step / change / reason):

(for Revision 0, describe purpose)

Prepared by: Date:

Optional Reviews: (Check those desired)

Tech Review: Date:

Group 1 lead: Date:

Approved by: Date:

Training Coordinator Date:

TR-8.8.5 Pagei

.- +,

l .

SIMUL ATOR IlOOK PREPARATION CilECKl.lST All simulator books verified current against current index and all procedures in the books.

Unit I books EOP/ECA CSP Abnormal Operating Procedures Operating Procedures Refueling Procedures Reactor Engineering instructions Reactor Operating Data llook Technical Specifications Alarm Response Book C01/lC03/lC04/lC20 litender Book Unit 2 books EOP/ECA CSP Abnormal Operating Procedures t Operating Procedures

, Refueling Procedures Reactor Engineering instructions Reactor Operating Data Book Technical Specifications Alarm Response Book C02/2CO3/2C04/2C20 Blender Book DSS / DOS books EPIP Emergency Plan Technical Specifications Operating instructions Standing Orders /Special Orders IIcalth Physics Procedures Fire Protection Manual Setpoint Document Duty and Call Handbook

__ RMS Alarm Response Book QA Procedure Manual QA Policy Manual EOP Background Document ECA Background Document CSP Background Document Admin Policy Manual TR-8.8.6 Page1

• E SII,1ULATOR llOOK PREPARATION CilECKLIST (cont.)

Instructor booth books EOP/ECA CSP Abnormal Operating Procedures Operating Procedures Reactor Engineering instructions Reactor Operating Data Book Technical Specincations Setpoint Document EOP Background Document ECA Background Document CSP Background Document Admin Policy Manual Extra procedure copies in the filing cabinets and form books.

s (15)lCP 10.2 (15) EPIP 1.1 (15) EPIP 1.1.1 (15) EPIP 1.3 (15) NRC NotiGeation Form Miscellaneous material supplies.

(10) Pads of paper (2 boxes) Pens Extra light bulbs available Simulator prints.

f- NOTE: Prints should be verified current to the Controi Room copies.

Primary system drawings Secondary system drawings (Unit I and Unit 2)

Secondary system drawings common i Logie diagrams TR-8.8.o Page 2

- - _ _ _ - _ _ _ _ _ - _ _ _ _ _ -