ML20093G130
| ML20093G130 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/25/1983 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20093G104 | List: |
| References | |
| 6211-ADM-2611.0, NUDOCS 8410150366 | |
| Download: ML20093G130 (55) | |
Text
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j ADMINISTRATIVE MANUAL 6211-tDM-2511.03 Title Revision No.
T!!I-I DIRECT SENIOR REACTOR OPERATnR TRAINING PROGRA!!
0-00
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Applicability / Scope Responsible Office DIRECT SENIOR REACTOR OPERATOR CANDIDATES TRAINING DEPARTMENT This document is important to safety 0 Yesy No Effective Date List of Effective Pages PAGE REVISION PAGE REVISION PAGE REVISION h
1.0 0-00 13.0 0-00 35.0 0-00 f
2.0 0-00 14.0 0-00 36.0 0-00 3.0 0-00 15.0 0-00 37.0 0-00 j-4 4.0 0-00 16.0 0-00 38.0 0-00 5.0 0-00 17.0 0-00 39.0 0-00 6.0 0-00 18.0 0-00 40.0 0-00 7.0 0-00 19.0 0-00 41.0 0-00 3.0 0-00 20.0 0-00 42.0 0-00 0.0 0-00 21.0 0-00 43.0 0-00 10.0 0-00 22.0 0-00 44.0 0-00 11.0 0-00 23.0 0-00 45.0 0-00 12.0 0-00 24.0 0-00 4C.n 0-00 13.0 0-00 25.0 0-00 47.0 0-00 14.0 0-00 26.0 00 43.c 0-00 15.0 0-00 27.0 0-00 49.0 0-00 16.0 0-00 23.0 0-00 50.0 0-00 17.0 0-00 29.0 0-00 51.0 0-00 18.0 0-00 30.0 0-00 52.0 0-00 19.0 0-00 31.0 0-00 53.0 0-00 10.0 0-00 32.0 0-00 54.0 0-00 11.0 0-00 33.0 0-00 55.0 0-00 12.0 0-00 34.0 0-00 56.0 0-00 Signature Concurnng Organizational Element Date originator [hhd Technical Programs Specialist
- t//4 /r3 Concurred by N M-Operator Training Manager 2 d.f//f l
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Sup. Licensed Oper.Trng Unit I j/rs,D L
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ADMIlilSTRATIVE MANUAL 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 TITLE: TMI-I DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 1.0 PURPOSE The purpose of the Direct Senior Reactor Operator Training Program is to pmpare qualified personnel to perfonn senior reactor operator duties.
2.0 SCOPE / APPLICABILITY This procedure applies to all Direct Senior Operator candidates.
Personnel placed in this program will normally fill job descriptions which do not require f requent cor. trol room participation.
3.0 DEFINITIONS 3.1 Candidate - An individual recognized by the Manager, Plant Operations as a potential Senior Reactor Operator. Members shall also have approval of his/her insnediate supervisor.
1' 3.2 Extra-Person - A candidate assigned to an operating shift for on-the-job training whose presence is not required to perfonn specific, non-training related tasks.
3.3 Task Examiner - Any individual who, due to his qualifications and I
experience, is selected to certify knowledge requirements of this
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program.
3.4 Instructor - An instructor f rom the Operator Training Section of the i
Training Department or a " guest" instructor whose expertise in a i
specific subject arta, e.g., a systems engineer, has resulted in his assignment, approved in writing by the Operator Training Manager or Manager Plant Training to present material on that subject area.
4.0 RESPONSIBILITIES l
4.1 The Shif t Supervisor is responsible for the following:
a)
Assignment of individuals as alternate task examiners. (A copy i
of this assignment list shall be forwarded to the Supervisor, Licensed Operator Training. )
l b)
Verifying adequate level of achievement and progress by the i
license candidates on the OJT phase of the program.
4.2 The Su 3ervisor, Licensed Operator Training, TMI-1, is responsible for the following:
a)
General supervision of the development and conduct of t!e Direct SR0 Training Prugram.
b)
Approval of the development, coordination, scheduling and 2
administration of the Direct SRO Training Program, including course outlines, lesson plans, student handouts, simulator 5
training, and evaluation exams.
E c)
Scheduling classes, students, classroom and facilities necessary E.
to conduct the training program.
d)
Interfacing with the Operations Department in all matters l
impacting the training programs.
e)
Assuring that the program content is updated and revised to meet current requirements and supervising revision of the program a
content, descriptions, lesson plans, and exams.
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 f)
Evaluation of course instruction and 1tcense candidate progress i
to detennine the effectiveness of the training pmgram and reporting these evaluations to the Operator Training Manager.
-g)
Maintaining the necessary recons and reports of training.
h)
Developing and conducting oral exams.
i 1)
Evaluation of candidate critiques of the training received.
i 4.3 The Operator Training Manager is responsible for the following:
a)
Assuring the quality of the Direct SRO Training Program by written approval of materials including course outline, lesson plans, student handouts, simulator training, quizzes and exams and their compatability with the Direct SR0 Training Program.
b)
Certification of candidates in accon ance with AP 1058.
4.4 The Manager, Plant Training is itsponsible for the following:
a)
To ensure that the training program is developed to meet the requirements established by the DirectorsTMI I, through the Manager, Plant Operations, and that proper reccords and documentation are prvvided and maintained.
b)
Certification of candidates in accordance with AP 1058.
4.5 The Manager, Plant Operations is responsible for the following:
a)
To ensure that the overall level of training of pla'nt operators is satisfactory through the approval of program content, schedules and administrative procedurts.
b)
To evaluate candidates at the completion of the simulator program on their proficiency to direct licensed activities.
c)
Certification of candidates in accordance with AP 1058.
4.6 The Director-TMI I is responsible for the following:
a)
Final certification of candidate in accordance with AP 1058.
5.0 REFERENCES
i 5.1 American Nuclear Standard (ANS) 3.1, Rev. 01/17/78, Selection, Qualification and Training of Personnel for Nuclear Power Plants.
5.2 Code of Federal Regulations, Section 10CFR55. Rev. 9/1/80, " Operator l
Licenses".
5.3 Regulatory Guide 1.8, Draft Rev. 9/80, Personnel Qualification and Training.
5.4 Administrative Procedure 1058, Requirements for Certification of Candidates for NRC Operator Licenses.
5.5 NUREG 0737, Clarification of TMI Action Plan Requirements.
E 3 6.0 ATTACHENTS 7
6.1 Appendix A - Systems Guide Lists 5
6.2 Appendix B - Licensed Operator DJT and System Checkouts l
6.3 Appendix C - Administrative Procedure and Qualification Checklist 6.4 Appendix D - Outbuildings Checklist E
6.5 Appendix E - Primary Systems Checklist i
6.6 Appendix F - Secondary Systems Checklist
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6.7 Appendix G - Watchstanding Checklist i
6.8 Appendix H - Oral Exam Summary Sheet f
6.9 Appendix I - Shift Foreman Trainee Duties Checklist A000105011 52 3.0
Number uusiesingAbwHI" w ggPy u Ks i a c: MA 6211-ADM-2611.03 Title Revision No.
THI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 6.10 Appendix J - Designation of Foreman as Final DJT Examiner 6.11 Appendix K - Simulator Training 7.0 PROGRAM DESCRIPTION 7.1 P re requisites:
All candidates for Dimet Senior Reactor Operator shall:
1.
Possess a degree in Engineering or applicable science.
2.
Have four years of msponsible power plant experience.
Responsible power plant experience should be that obtained as a contml room operator (fossil or nuclear) or as a power plant staff engineer involved in the day-to-day activities of the facility. A maximum of two years power plant experience may be fulfilled by academic or related technical training, on a one-forsone time basis. Two years shall be nuclear power plant experience.
3.
Complete a minimum of three months perfonning the duties of a Senior Reactor Operator while under instmction as an extra person in the contml room.
4.
Satisfactorily meet the minimun medical requirements for licensed personnel as specified in 10CFR55.
7.2 Sequence
1.
The pmgram consists of the following:
a)
Q)T - 3 months b)
Decision Analysis (3 days) c)
Supervisory Development (1 week) d)
Simulator Training (3 weeks)
(Candidates who possess a Startup Certification will only complete a two (2) week program.)
e)
Classroom - as determined by Supervisor Licensed Operator Training, TMI-1.
The length of the Direct SRO program is dependent on the candidates experience and availability. The requirements listed above are essential to the program and must be completed. The time necessary to complete the on-the-job training tasks may vary from candidate to candidate, and as a result time to completion may vary.- In no case shall the program exceed eighteen (18) months.
_E E
Due to the diversity of nuclear experience that will be 9
encountered from candidate to candidate, and the time j
requirements of regularly assigned job func'tions, the comittment of time devoted to the prugram may vary.
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Courses in Decision Analysis and Supervisory Development may be waived by the Operator Training Manager due to candidates g
mvious experience.
he program concludes with the NRC examination..
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AOOO105011 52 4.0 1
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6211-ADM-2611.03 h
Revision No.
THI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 7.3 Program Objectives:
1.
Conduct training in the subject areas listed below as required to enable the trainee to demonstrate through written and oral 1
examinations, completion of specified practical factors, and completion of an operating examination, the ability to direct the activities of licensed operators safely and competently and to obtain an NRC Senior Reactor Operator license.
Subject Amas a)
Supervisory course in decision analysis / supervisory development.
b)
Supervisory control room and plant operating experience, dincted by specific task assignments and licensed senior operators.
c)
Reactor Theory d)
Plant Design and Operating Characteristics e)
Plant Contrul Systems f)
Radiation Control and Safety g)
Plant Transients h)
Recognizing and Mitigating Core Damage 1)
Simulator Training 2.
Verify that the candidate has received or otherwise demonstrated knowledge equivalent to those candidates who have completed the TMI-1 Senior Reactor Operator Replacement Training Program and its prtcursors.
7.4 Outline
1.
On-the-Job Training a)
Secondary Systems b)
Primary Systems c)
Administrative Procedums d)
Nonna1, Abnormal and Emergency Operating Procedures e)
Technical Specifications f)
Shift Fortman Duties 2.
Classroom Training Classroom Training will be provided to meet needs established by l
the Supervisor, Licensed Operator Training. A review of the candidates college level courses and training in nuclear related fields shall be made to determine the extent of the program needed. The topics listed below are to be used as a guide for determining needed classrvom training.
E a)
Reactor Theory Review l
5 NeutrVns and Neutron Interactions 5
Sol ving Exponential Equations l
j Multiplication Factors Reactor Kinetics Reacti vity
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l Subcritical Multiplication Neutron Sourtes g
Reactor Period and Start Up Rate g
Problem Solving in Reactor Kinetics l
Reacti vity Cnofficients A000105011 52 5.0 l
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NuSlearDNl "Ablq!I qTRAT VE MANUALl"1"c3^eGPY 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 Flux Distribution DNB, Fg, Control F H Reactor Fuel Assemblies and Contml Rods Transients and Effects on Fuel Assemblies & Contml Rod Fission Product Poisons Reactor Transient Analysis Excom Nuclear Instruments Fission Product Gasses and Fission Pmducts b)
Heat Transfer and Fluid Flow, Themodynamics Heat Transfer Pmperties of Fluids Steam Tables Core and Plant Parameters, Nomal and Transient c)
General Categories Facility Incidents Emergency Plan Secu rity Technical Specifications Administrative Procedures Emergency, Abnormal and Normal Operating Proce'dures, including Abnormal Transient Operating Guidelines Primary and Secondary Chemistry Review Recognition and Mitigation of Consequences of Severe Core Damage Change Modifications d)
Radiation Control and Safety Radioactivity and Radiation Effects of Radiation Radiation Exposure Limits Radiation Protection Pmblems Radiation Instruments e)
Reactor Control RG5 Instrument Failufts Integrated Control System (ICS)
ICS Transients 7.5 Administration 7.5.1 Program Presentation 1.
On-the-Job Training 5
a)
The on-the-job training program consists of j
preselected and day to day tasks which involve 9
participation by the Direct Senicr Reactor Operator candidate in Shift Forema related o
E activities designed to reinfort:e classroom study, maximize new learning experiences, and stimulate 3
inte rest.
b)
Primary verification of OJT tasks shall be by
_o oral checkout of the candidate on individual task 3
items by a task examiner. Task Examiners for o
itom: in Annandir R t hall hp liennted Rn't and j
AOOO10501132 l
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 SR0's. Task Examiners for Appendix D shall be Qualified Auxiliary Operators.
Final verification shall be by oral and written checkout of task sheet sections by the Shift Supervisor (or Shift Foreman as designated in writing by the Shift Supervisor, using the Sumary Sheet in Appendix J), or by a Licensed SR0 Instructor.
c)
During the DJT phase the liunse candidates shall be assigned to various shif ts with the appmval of Manager, Plant Operations. During this phase, the candidate shall assume Shift Foreman duties under instruction and perfom other tasks as assigned.
d)
The level of perfomance for each DJT Task is designated in the text or to the right of the description in parenthesis. The following are levels of perfomance in ortier of preference:
(P) = Pe rfo rm. The candidate shall perform each task under the direct supervision of a qualified operator. This level of performance is the most preferred due to the hands-on experience gained by the candidate.
(S) = Simulate. The candidate shall simulate each task under the direct supervision of a qualified operator. The simulation shall be done as much as possible in the vicinity of the actual component or e quipment. Hands-on training, without actual manipulation of valves, breakers, etc is encouraged.
When simulating Emergency and Abnormal Pmcedures the following is required.
1.
Find all indications mentioned.
l 2.
Locate all items used to verify that automatic actions have occurred.
i 3.
Locate all controls necessary to 5
perform all imediate manual and subsequent actions.
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4.
Walk thmugh all Emergency and 5
Abnormal Pmcedures and note l
E indicators, check automatic actions, 7
and simulate performing manual r
l l
actions f rom memo ry.
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y gungflg % Q M &eGPY l ADMINISTRATIVE MANUAL 6211-ADM-2611.03 Title Restision No.
THI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 (D) = Discuss. The task examiner shall examine the candidate.on the items to evaluate the candidate's overall understanding of the procedu re.
i Using the procedure as a reference the I
candidate shall be able to discuss:
1 1.
Limits and precautions 2.
Major steps in procedure 3.
Basis for procedure sequence.
When an option of the level of performance is offered the examiner shall designate by cirtling which one was done.
e)
Signatures obtained to meet the requirements of.
this pmgram are valid for eighteen (18) months.
After that time the task must be repeated.
2.
Classroom Training a)
Classroom training shall be conducted by qualified. instructors using approved lesson plans.
b)
The candidate will be responsible for all material presented.
3.
Simulator A three (3) week Simulator Program will be utilized to reinforce classroom and OJT concepts and to develop an understanding of integrated plant response.
One week of the Simulator Prugram will be devoted to Startup Ce rtification, as required.
a)
Candidates for Direct SRO will be evaluated by l
the Manager, Plant Operations or his designated representative at the c:mpletion of the simulator program on their proficiency to direct licensed acti vities. This evaluation is pa rt, of the certification process.
The use of the simulator for training is addressed in Appendix K.
7.5.2 Evaluation Criteria
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1.
On-The-Job Training a)
Comprehensive oral checkouts shall be administered by the task examiners for specific task sign-offs and documented by the examiner's 5
signatu re.
3 b)
The ultimate responsibility for detemining 5
adequate achievement by the studant rests with 5
the Shift Supervisor, or Licensed SRO Instructor who shall evaluate the performance of the candidate by final oral check out and/or written r
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questioning at the end of each section of the OJT i
task (i.e. Primary Systems, Electrical Systems),
g using the Oral Examination Summary Sheet in AOOO105011 S2 8.0
Nu21e@@DMG'i@cGPY ADMINISTRATIVE MANUAL 6211-ADM-2611.03 Tih Revision No.
TMI-l DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 Appendix H.
This fom shall be retained in the candidate's pennanent training file.
c)
All tasks which cannot be performed are to be simul ated. Perfomance or simulation of a task shall not alone constitute successful completion of the task. Discussion and oral questioning by the task and final examiners must be included to substantiate successful completion of the task.
d)
Individuals failing to achieve a " pass" grade on the OJT Oral Exam checkouts shall be:
1.
Infonned of their weak areas and given direction on the material that they should study to upgrade their performance.
2.
Re-examined within two weeks of the initial failure.
NOTE: Details of weak areas and scheduled date for re-exam must be forwarded to the Supervisor, Licensed Operator Training.
If an individual fails the second section check-out the Manager, Plant Operations, Operator Training Manager and candidate's supervisor shall review the Direct SRO license candidate's everall progress and performance and detennine the correctiw action to bo taken.
l 2.
Written Examinations Written examinations shall be administered by representatives of the Operator Training Section as required by the Supervisor, Licensed Operator Training. Questions shall cover that material presented in the classroom, material specified for self study, and the material identified on the task sheets.
A passing grade of 80% is mandatory for all written examinations. A grade of less than 80% shall require candidate counseling by the instructor responsible for l
noted weak areas on the candidate's exam with j
suggested corrective actions that will upgrade the candidate's performance. A re-exam vill be 5
administered within two weeks. If a candidate fails ii the second exam the Manager, Plant Operations,
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Operator Training Manager, and the candidate's 5
supervisor shall evaluate the SRO license candidate's l
E performance and decide on the corrective action to be
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i taken.
E 3.
Final Examination 5
A comprehensive written and oral examination shall be administered by the Training Department at the g"
g conclusion of the training program. An 807, overall l
A0001050st S2 9.0
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RN m MANUAL 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 average and a 70% on individual sections is mquired for the satisfactory completion of the written phase.
The oral examination should nomally consist of two phases; a " walk through" phase, administered by an Instructor selected by the Supervisor, Licensed Operator Training, and a " board" composed of Instructors designated by the Supervisor, Licensed Operator Training and the Manager, Plant Operations or his selected representative. A " pass" grade is mquired for the oral exam substantiated by documentation with the Oral Examination Sumary Sheets in Appendix H.
Upon completion of these exams, the candidate's training files and Training Department recomendations shall be forwarded to the Director - TMI I, who shall certify the candidate for NRC examination or, in the case of unsatisfactory completion of the program, decide on the cormctive action to be taken.
7.6 Changes and Lesson Plan Correstion The program shall be maintained to reflect the following:
a)
Changes in regulatory requirements b)
Changes in applicable codes, standards and guides c)
Significant experiences at the facility d)
Significant experience throughout the industry e)
Remedial action recommended by review / audit findings f)
Regularly scheduled participant critiques.
Changes will be incorporated per the applicable Training Department Procedu re.
/ Program Scheduling The prograra will be scheduled as needed.
7.8 Records and Reports 1.
A Training Program Administrative fom shall be completed and submitted to the Administrative Section for each classroom lecture or lesson by the instructor who presented the material.
2.
Current and past schedules, lesson plans, student handouts, completed OJT task sheets, exam keys and completed exams and quizzes, both written and oral, as well as any additional pertinent qualification records shall be maintained on file in the Training Department.
5 The Candidate Progress Report shall be maintained at the 5
training center. Copies of the updated report shall be 5
submitted by the Supervisor, Licensed Operator Training to the 5
Manager, Plant Training and Manager, Plant Operations via the 3
Operator Training Manager on a monthly basis, or more f requently on a case-by-case basis if requested by any of the reviewing i
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A000105011 32 10.0
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Nuslestol N L 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 7.9 Evaluation 1.
At the conclusion of each month of training the license candidates will be asked to complete.a training critique fonn to assist in program evaluation. Tise completed critiques shall be reviewed by the Supervisor, Licensed Operator Training and forwarded, along with recommendations or corrective action taken to the Manager, Plant Training, via the Operator Training Manage r.
2.
The Direct SR0 Training Pmgram and its contents shall be reviewed and updated at the end of each program presentation by the instructors presenting the course and the Supervisor, Licensed Operator Training. He shall report the results of this review, along with reconsnendations or corrective action taken to the Manager, Plant Training, via the Operator Training Manager.
During the presentation of the course no changes in course content shall be made without prior apprvval of the Operator Training Manger.
3.
Annually an intemal team will be formed by the Supervisor, Licensed Operator Training to review the Direct SR0 Training Program. The review team should consist of personn.el from the Operations and Training Departments. The team will assess the adequacy of the program for:
Meeting new requirements Adequacy of recorts Quality of material and presentations Effecti veness In conducting the review, the team may use any records maintained by the Training or Operations Departments to assist them. These may include:
NRC Inspections QA Audits Other Audits Regulatory Changes Industry Experience License Candidate Critiques The review team shall report the results to the Manager, Plant Training and the Manager, Plant Operations via the Supervisor, Licensed Operator Training and the Operator Training Manager.
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX A SYSTIMS CHECK 0UT GUIDELINE When studying for a system checkout the candidate should be able to do the following:
1.
State the functions 2.
State setpoints and interlocks 3.
State the design limits and parameters during normal operations.
4.
Draw a one line diagram including:
a.
Major components (pumps, breakers, val ves).
b.
Power supplies to components c.
System intertonnections d.
Meters and gageboards (as applicable) 5.
Describe physical location of major components (where applicable) 6.
State Technical Specifications and basis for each 7.
Describe system response during nomal and abnomal conditions.
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i AOOO10501152 12.0
Nucimgl ADMI ISTRATIVE MANUAL &*FOAGOPY 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 1.0 PRIMARY PLANT PRACTICAL FACTORS TASK EXAMINER DATE 1.1 REACTOR COOLANT SYSTEM (1) 1.1.1 RCS FILL AND VENT 1103-2 (S) 1.1.2 DRAINING AND N2 BLANKETING OF RCS SYSTEM 1103-11 (S) 1.1.3 RCS LEAKAGE 13U3-1.1 (S) 1.1.4 LOSS OF RC/RC PRESSURE 1202-6A (S) 1.1.5 LOSS OF RC/RC PRESSURE 1202-6B (S) 1.1.6 LOSS OF RC/RC PRESSURE 1202-6C (S) 1.1.7 LOSS OF HIGH ACTIVITY IN RC 1202-11 (S) 1.1.8 INADEQUATE CORE COOLING 1202-39 (S) 1.1.9 LOSS OF RC FLOW /RC TRIP 1202-14 (S) 1.1.10 VIBRATION AND LOOSE PARTS 1203-40 (S) 1.2 REACTOR COOLANT PUMPS AND SEALS (1)
- 1. 2.1 RCS PUMP AND MOTOR MALFUNCTIONS 1203-16 (S) 1.2.2 ESTABLISH ALL CONDITIONS NECESSARY TO RUN REACTOR COOLANT PUMPS (START &
STOP RCP'S) (P OR S) 5 (1) Systems Checkout. All signatures by licensed SR0 or RO.
5 5
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AOOO105011 92 13.0
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62II-ACM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR alt CHECKLIST 1.0 PRIMARY PLANT PRACTICAL FACTORS CONTINUED TASK EXAMINER DATE 1.3 REACTOR VESSEL CONSTRUCTION (1) 1.4 MAKEUP AND PURIFICATION (1) 1.4.1 LOSS OF REACTOR COOLANT MAKEUP 1203-15 (S) 1.4.2 PERFORM AN RCS B0 RATION AND CALCULATION 1.4.3 PERFORM RCS DILUTION 1.4.4 PERFORM RCS DEB 0 RATION 1.4.5 PERFORM RCS BORON CHANGE FOR ALL RODS OUT POWER REDUCTION TO 50%
(With Xe) 1.4.6 SOLUBLE POISON CONCEN-TRATION CONTROL 1103-4 (S) 1.4.7 MKEUP AND PURIFICATION 1104-2 (D) 1.5 DECAY HEAT REMOVAL (1) 1.5.1 LOSS OF DECAY HEAT REMOVAL 1202-35 (S) 1.5.2 DECAY HEAT REMOVAL 1104-4 (D) 1.6 CORE FLOOD (1) 1.6.1 CORE FLOOD SYSTEM 1104-1 (D)
T.7 PRESSURIZER AND PRESSUPI RELIEF (1) 1.7.1 PRESSURIZER FAILURE 1202-29 (S) 5 1.7.1 PRESSURIZER OPERATION j
1103-5 (D) 9 5 (1)
Systems Checkout - All signatures by licensed SRO or R0 5
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A000105011 92 14.0
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TPAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 1.0 PRIMARY PLANT PRACTICAL FACTORS CONTINUED TASK EXAMINER DATE 1.8 ONCE THROUGH STEAM GENERATORS (1) 1.8.1 OTSG TUBE RUPTURE 1202-5 (S) 1.8.2 INADVERTENT CLOSURE OF MAIN STEAM ISOLATION VALVE 1202-42 (S) 1.8.3 LOSS OF FEED TO OTSG 1202-26A (S) 1.8.4 LOSS OF FEED TO OTSG 1202-268 (S) 1.8.5 OTSG FILL, DRAIN, LAYUP 1106-16 (D)
FINAL VERIFICATION:
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/DATE (1)
Systems Checkout. All signatures by licensed SRO or R0.
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Number LkIMpITRAlHEMANUALa "rW COPY Nu2IelRDfl 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR CUT CHECKLIST TASK EXAMINER DATE 2.0 PRIMARY SUPPORT SYSTEMS 2.1 NUCLEAR SERVICE RIVER WATER (1) 2.1.1 RIVER WATER FAILURE 1203-19 (S) 2.1.2 NUCLEAR RIVER WATER 1104-30 (D) 2.2 DECAY HEAT RIVER WATER (1) 2.3 DECAY HEAT CLOSED COOLING (1) 2.3.1 DHCC 1104-13 (D) 2.4 INTERMEDIATE CLOSED COOLING (1) 2.4.1 LOSS OF INTERMIDIATE COOLING 1202-17 (S) 2.4.2 INTEREDIATE CLOSED COOLING 1104-8 (D) 2.5 RADIATION MONITORING SYSTEM (1) 2.5.1 EXCESSIVE RADIATION LEVELS 1202-12 (S) 2.5.2 EVALUATE AND FOLLOW-UP RMS ALARMS 2.5.3 RADIATION MONITORING l
CHECKS 1303-4.15 (S) 2.6 FUEL HANDLING (1) 2.7 WASTE DISPOSAL - SOLID (1) 2.7.1 SOLID WASTE DISPOSAL 1104-28B 2.8 WASTE DISPOSAL LIQUID (1) 2.8.1 INITIATE, MAKE, AND COWLETE A LIQUID l
WASTE RELEASE (P) OR S
(S) (1104-29 5
2.8.2 LIQUID WASTE DISPOSAL 7
1104-29) (D) 5 E (1)
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Signature Required by Chem. Tech. Perfonning Sample.
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1 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM
'0-00 i
s APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST
'N 2.0 PRIMARY SUPPORT SYSTEMS CONTINUED TASK EXAMINER DATE 2.9 PRIMARY SUMPS AND DRAINAGE (1) 2.9.1 PLANT SUWS AND DRAINAGE 1104-40 (D) 2.10 HYDROGEN RECOMBINER (1) 2.10.1 HYDR 0 GEN RECOMBINER 1104-62 (D) 2.11 HYDR 0 GEN AND NITROGEN NUCLEAR (1) 2.11.1 NITROGEN SUPPLY
^
1104-26 (D) 2.11.2 HYDR 0 GEN ADDITION 1102-12 (D) 2.12 PRIMARY CHEMISTRY CONTROL (1) 2.12.1 ASSIST IN RECOGNIZING &
^
TAKING ACTION FOR OUT OF SPECIFICATION CHEMISTRY (P) OR (S) 2.12.2 CHEMICAL ADDITION NUCLEAR 1104-47B (D) g 2.13 FLUID BLOCK (1) 2.13.1 FLUID BLOCK 1104-20 (D) s, 2.14 PRIMARY SAWLING (1) 2.14.1 OBSERVE DRAWING AND ANALYZING A PRIMARY SAWLE (2) 2.14.2 NUCLEAR PLANT SAWLING 1104-43 (D) 5 2.15 SPENT FUEL COOLING (1) 5 2.15.1 SPENT FUEL CLEANUP j
PROCESS 1104-29C (D) p C"
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TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 i
APPENDIX "B"
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LICENSED OPERATOR OJT CHECKLIST 2.0 PRIMARY SUPPOR1 SYSTEMS CONTINUED TASK EXAMINER DATE 2.16 NUCLEAR SEdVICES CLOSED COOLING (1) 2.16.1 NSCC SYSTEM FAILURE (1203-20 (S) 2.16.2.HSCC 1104-11 (D )
g 2.17 WASTE DISPOSAL GAS (1) 2.U.1 INITIATE, MAKE AND COW LETE A LIQUID WASTE RELEASE (P) 2.17.2 HASTE DISPOSAL - GASEOUS.
1104-27 (D)
FINAL YERIFICATION:
SHIFT SUPERVISOR
/DATE (1)
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TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM
' 0-00 APPENDIX "B" LICENSED OPERATOR DJT CHECKLIST 3,0 SECONDARY SYSTCMS PRACTICAL FACTORS TASK EXAMINER DATE 3.1 MIN STEAM (1) 3.1.1 BE ABLE TO USE STEAM TABLE PARAETERS AND PLANT PARAMETERS -
PLOT A SECONDARY HEAT BALANCE 3.1.2 STEAM SUPPLY SYSTEM RUPTURE 1203-23 (S) 3.1.3 MIN STEAM 1106-14 (D) 3.2 AUXILIARY STEAM AND AUXILIARY BOILERS (1)
- 3. 2.1 ASSIST IN STARTUP OF SYSTEM (P) 0R (S) 3.2.2 AUXILIARY BOILERS 1106-4 (D) 3.2.3 AUXILIARY STEAM CROSS CONNECTION 1106-19 (D) 3.3 E/, TRACTION STEAM (1) 3.3.1 EXTRACTION STEAM HEATER YENT AND DRAINS 1106-12
-(D) 3.4 HEATER VENTS AND DRAIN (1) 3.4.1 PLACE HEATER DRAIN puffs IN SERVICE (P) OR (S) 3.4.2 EXTRACTION STEAM, HEATER VENT AND DRAINS 1106-12 (D) 5 3 3.5 FEEDWATER (1)
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3.5.1 ASSIST IN STARTUP OF 5
SYSTEM (P) OR (S) 3.5.2 FEEDWATER SYSTEM 1106-3 i
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MA 6? I ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 3.0 SECONDARY SYSTEMS PRACTICAL FACTORS CONTINU$D TASK EXAMINER DATE 3.5.3 STARTUP AND PLACE A FEEDWATER PUW IN SERVICE (P) OR (S) 3.6 EMERGENCY FEEDWATER (1) 3.6.1 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.6.2 EMERGENCY FEED 1106-6 (D)
S.7 CONDENSATE (1) 3.7.1 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.7.2 HIGH CATION CONDUCTIVITY IN CONDENSATE 1203-5 (S) 3.7.3 CONDENSATE SYSTEM 1106-2 (D) 3.8 CONDENSER AIR EXTRACTION (1) 3.8.1 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.8.2 MAIN AND AUX. VACUUM SYSTEM 1106-15 (D) 3.9 GLAND SEAL (1) 3.9.1 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.9.2 TURBINE GLAND SEAL STEAM SUPPLY SYSTEM 1106-10 (D) l 3.10 MAIN TURBINE - GENERATOR (1) 3.10.1 PLACE MAIN TURBINE ON E
LINE AND PLACE IN AUTO 3
(INCLUDING WARMUP) 5 (P) OR (S) (1106-1) 5 3.10.2 TURBINE TRIP TEST l
E 1106-1.0 (P) OR (S) i 7.10.3 TURBINE TRIP 1203-3 (S)
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECXLIST 3.0 - SECONDARY SYSTEMS PRACTICAL FACTORS CONTINUED TASK EXAMINER DATE 3.10.4 TURBINE GENERATOR 1106-1 (D) 3.11 TURBINE LUBE DIL (1) 3.11.1 TURBINE LO PUlflNG 1106-9 (D) 3.11.2 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.11.3 TURBINE OIL CONDITIONER
& SUPPLY 1104-34 (D) 3.12 GENERATOR STATOR COOLING (1) 3.12.1 STATOR COOLING SYSTEM 1106-7 (D) 3.13 GENERATOR CORE MONITOR (1)'
3.13.1 TURBINE GENERATOR 1106-1 APP. C.3 (D) 3.14 GENERATOR GAS AND YENTS (1) 3.14.1 HYDROGEN SEAL OIL AND GAS 1106-8 (D) 3.14.2 ASSIST IN STARTUP OF THE SYSTEM (P) OR (S) 3.15 GENERATOR SEAL OIL (1) 3.15.1 HYDROGEN SEAL OIL AND GAS 1106-8 (D) 3.15.2 ASSIST IN STARTUP OF l
THE SYSTEM (P) OR (S) 3.16 ELECTR0 HYDRAULIC CONTROL (1) l 3.16.1 TURBINE HIGH PRESSURE 3
FLUID SYSTEM 1106-17 (D) 7 3.16.2 ASSIST IN STARTUP OF 5
THE SYSTEM (P) OR (S) 9 FINAL VERIFICATION:
f SHIFT SUPERVISOR
/DATE f (1)
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A000105011 82 21.0
Number FyF1 fTRAiMntCEPY
- Y Nusleg ikt NUAL 6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPEPATOR G)T CHECKLIST 4.0 SECONDARY SUPPORT SYSTEMS TASK EXAMINER DATE 4.1 SECONDARY SERVICE RIVER WATER (1) 4.1.1 SSRW 1104-31 (D) 4.2 ECHANICAL DRAFT COOLING TOWER (1) 4.2.1 MDCT 1104-37 (D) 4.2.2 ASSIST IN S1 ARTUP OF SYSTEM (INCLUDING TElf.
CONTROL AND DEICING (P) OR (S) 4.3 SCREENHOUSE EQUIPENT (1) 4.3.1 SCREENHOUSE EQUIPMENT 1104-33 (D) 4.4 CONDENSER CIRCULATING WATER (1) 4.4.1 CIRCULATING WATER 1104-9 (D) 4.4.2 ASSIST IN STARTUP OF SYSTEM (INCLUDING DEICING (P) OR (S) 4.5 CIRCULATING WATER CHLORINATION AND CHEM. FEED (1)
- 4. 5.1 CIRC. WATER CHLORINATION 1104-35 (D) l 4.6 AE RTAP (1) f 4.6.1 CIRCULATING WATER l
1104-9 (1) l 4.6.2 ASSIST IN STARTUP OF l
SYSTEM (P) OR (S) 5 4.7 CYCLE MAKEUP PRETREATENT (1) 5 4.7.1 CYCLE MAKEUP PRETUATMENT l
5 1104-22 (D) 5
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6211-ADM-2611.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 4.0 SECONDARY SUPPORT SYSTEMS CONTINUED TASK EXAMINER DATE 4.8 CYCLE MKELP DEMINERALIZER (1) 4.8.1 CYCLE MAKEUP DEMINERALIZER 1104-23 (D) 4.9 DEMINERALIZED WATER (1) 4.10 DOMESTIC WATER (1) 4.10.1 DOMESTIC WATER 1104-49 (D) 4.11 RECLAIMED MTER (1) 4.11.1 RECLAIMED WATER 1104-47A (D) 4.12 INSTRUENT/ CONTROL AIR (1)
~
4.12.1 INST./ CONT AIR 1104-25 (D) 4.12.2 LOSS OF INSTRUMENT AIR 1202-36 (S) 4.13 STATION SERVICE AIR (1) 4.13.1 STATION SERVICE AIR 1104-42 (D) 4.14 INDUSTRIAL WASTE FILTER SYSTEM (1) 4.14. ".
IWFS 1104-508 (D) 4.15 INDUSTRIAL WASTE TREATMENT (1) 4.15.1 IWTS 1104-50A (D) 4.16 SECONDARY CHEMISTRY CONTROL (1) 5 4.16.1 OBSERVE DRAWING AND 5
ANALYZING A SECONDARY 5
SAW LE.
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TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 4.0 SECONDARY SUPPORT SYSTEMS CONTINUED TASK EXAMINER DATE 4.17 SECONDARY SERVICE CLOSED COOLING (1) 4.17.1 SSCC 1104-12 (D) 4.17.2 SSCC SYSTEM FAILURI 1203-21 (S)
FINAL VERIFICATION:
5 Hit i SUPERVISOR
/DATE (1)
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Number NuslencjMyIpI3TK"W^t"OPY
'ASN MANUAL 6211-ADM-2611.03 g,
Revision No.
THI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 5.0 INSTRUENTATION AND CONTROL TASK EXAMINER DATE 5.1 CONTROL ROD DRIVE SYSTEM (1) 5.1.1 LOCATE AND OPERATE THE FOLLOWING SWITCHES ASSOCIATED WITH THE CONTROL ROD DRIVE SYSTEM 5.1.1.1 SAFETY RODS OUT BYPASS 5.1.1.2 GROUP 7 OUT LIMIT BYPASS 5.1.1.3 BORON DILUTE BYPASS 5.1.2 POINT OUT AND DESCRIBE THE C0WONENTS IN THE CRD CABINETS 5.1. 3 CRD SYSTEM 1105-9 (D) 5.1.4 CONTROL R0D MOVEMENT 1303-3.1 (P) OR (S) 5.1. S CRD EQUIPMENT FAILURES 1202=8 (S) 5.1.6 UNANTICIPATED CRITICALITY 1203-10 (S) 5.2 EXCORE NUCLEAR INSTRUENTS (1) 5.2.1 NUCLEAR INSTRUMENTS 1105-1 (D) 5.2.2 CHANGE INPUTS TO THE POWER RANGE RECORDER (P) SP 1302-1.1 5.3 INCORE NUCLEAR INSTRUENTS (1) 5.3.1 INCORE MONITORING SYSTEM 1105-5 (D) 5 5.3.2 INCORE NEUTRON DETECTORS fi SURVEILLANCE 1301-5.3 l
5 (P) s E (1) gYSTEM CHECK 0UT. ALL SIGNATURES BY LICENSED SR0 OR R0.
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Number Nuslege ")l3! 4pSTRAT;VE MANUALi"ND^e0PY A
l 6211-ADM-2611.03 Title Revision No.
THI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 5.0 INSTRUENTATION AND CONTROL CONTINUED TASK EXAMINER DATE 5.4 NON NUCLEAR INSTRUENTS (1) 5.4.1 RCS NNI 1105-6 (D) 5.4.2 CHANGE INPUTS FOR THE CONTROLLING RCS PRESSURE SIGNAL (P) 1105-6-3.4.3 5.4.3 CHANGE INPUTS FOR THE CONTROLLING RC FLOW SIGNAL (P) 1105-6-3.4.10 5.4.4 SELECT THE CONTROLLING TC'S FOR THE PUW INTER-LOCKS (P) 1105-6-3.4.5 5.4.5 DETERMINE THE STATUS OF -
RC PUW INTERLOCKS (P) 5.4.6 POINT OUT AND DESCRIBE ALL METERS, SWITCHES AND MODULES IN THE ICS/NNI CABINETS 5.5 REACTOR PROTECTION SYSTEM (1) 5.5.1 RPS 1105-2 (D) '
5.5.2 RESET REACTOR PROTECTIVE CHANNELS AFTER A TRIP (P) OR (S) 5.5 REACTOR PROTECTION SYSTEM CONTINUED 5.5.3 DETERMINE THE CAUSE OF A TURBINE TRIP (P) OR (S) l 5.5.4 DETERMINE WilCH RELAY l
CAUSED A GENERATOR TRIP l
FROM THE RELAY TARGET l
(P) OR (S) 5.5.5 POINT OUT AND DESCRIBE l
ALL METERS, SWITCHES AND l
E MODULES IN THE RPS 9
CABINETS 5
5.5.6 REACTOR TRIP 1202-4 (S)
(1)
SYSTEM CHECK 0UT. ALL SIGNATURES BY LICENSED SR0 OR R0.
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bl 62 1-ADM-2611.03 g
Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM n nn APPENDIX "B" LICENSED OPERATOR 0]T CHECKLIST 5.0 INSTRUENTATION AND CONTROL CONTINUED TASK EXAMINER DATE 56 EMERGENCY SAFEGUARDS ACUTATION SYSTEM (1) 5.6.1 ESAS 1105-3 (D) 5.6.2 EMERGENCY CHECKLIST (P) 5.6.3 EMERGENCY SAFEGUARDS ACTUATION SURVEILLANCE (P) 5.6.4 RESET AN ENGINEERED SAFEGUARDS CHANNEL AFTER A TRIP (P) OR (S) 5.6.5 POINT OUT AND DESCRIBE ALL METERS, SWITCHES, AN0 MODULES IN THE E.S.
CABINETS 5.7 INTEGRATED CONTROL SYSTEM (1) 5.7.1 ICS 1105-4 (D) 5.7.2 POINT OUT AND DESCRIBE ALL CONSOLE ICS INSTRUENTATION INPUT SWITCHES, INDICATORS AND RECORDERS 5.7.3 OPERATE ICS CONTROLS IN HAND (P)
E jFINAL VERIFICATION:
9 5HIF I SUPERVISOR
/DATE 5
b 5
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AOOO105011 32 27.0 i
NuciapitTwa@A6GPY ADMINISTRATIVE MANUAL 6211-ADM-2611.03 Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PRnt: DAM O 00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 6.0 ELECTRICAL SYSTEMS TASK EXAMINER DATE 6.1 BALANCE OF PLANT ELECTRICAL (1) 6.1.1 ELECTRICAL SYSTEM 1107-1 (D) 6.1.2 POINT OUT AND DESCRIBE COWONENTS AND THE ELECTRICAL FLOWATH IN THE SWITCHYARD AND RELAY HOUSE (INCLUDE OPERATIONS) 6.1.3 POINT OUT AND DESCRIBE
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C0WONENTS AND THE ELECTRICAL FLOWATH FROM THE MAIN TRANSFORMER THROUGH 6900 VOLT AND 4160 VOLT BUSSES AND 480 VOLT DISTRIBUTION (INLCUDE INTERLOCKS & OPERATIONS) 6.1.4 DEMONSTRATE UNDERSTANDING OF THE GUIDANCE FOR OPERATING SWITCHYARD BREAKERS (MANUAL IN CONTROL ROOM 6.1.5 WALKTHROUGH THE PROCESS FOR TRANSFERRING VITAL POWER BUSSES FROM NORMAL TO BACKUP POWER SUPPLY (1107-2-3.3.6) 6.1.6 EMERGENCY POWER
~
1303-4.16 (D) 6.1.7 BLACK 0UT 1202-2 (D) 6.1.8 BLACK 0UT 1202-2A (D) -
l 6.1.9 LOW SYSTEM (GRID) VOLTAGE 1203-41 (D)
E 6.1.10 LOAD REJECTION 1203-1 9
(D) 6.1.11 EMERGENCY ELECTRICAL o
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l Number 6211-ADM-2611.03 r
7;g, Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM n nn APPENDIX "B" LICENSED OPERATOR DJT CHECKLIST 6.0 ELECTRICAL SYSTEMS CONTINUED TASK EXAMINER DATE 6.1 BALANCE OF PLANT ELECTRICAL CONTINUED 6.2 DIESEL GENERATORS (1) 6.2.1 STARTUP AND SECURE A DIESEL OPERATOR, PLACE IN ES STANDBY (P) OR (5) 6.2.2 DIESEL GENERATOR 1107-3 (D) 5.3 120 VAC VITAL POWER AND D.C.
DISTRIBUTION (1) 6.3.1 POINT OUT AND DESCRIBE C0WONENTS AND ELECTRICAL
- FLOWPATH IN THE 120 VAC VITAL DISTRIBUTION SYSTEM.
BE ABLE TO DISCUSS INTER-LOCKS AND OPERATION.
(INCLUDE PLACING AN INVERTER IN SERVICE) 6.3.2 POINT OUT AND DESCRIBE COWONENTS AND 'THE ELECTRICAL FLOWATH IN -
THE 125/250 YAC DIST.
SYSTEM. BE ABLE TO DISCUSS INTERLOCKS AND OPERATION.
(INCLUD2 PLACING CHARGER IN SERVICE).
l W.4 ISOLATED PHASE BUS DUCT COOLING (1) a I
h INAL VERIFICATION:
o SHitI SUPERVISOR
/DATE 2
( 1)
SiSTEM CHECK 0UT. ALL SIGNATURES BY LICENSED SR0 OR RO.
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Number c
4 L 6211-ADM-2611.03 Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PDORDAM 0 APPENDIX "B" LICENSED OPERATOR GJT CHECKLIST 7.0 BUILDING SUPPORT SYSTEMS TASK EXAMINER DATE 7.1 REACTOR BUILDING EMERGENCY COOLING (1)
RB EMER. COOLING 1104-38 (D) 7.2 REACTOR BUILDING SPRAY (1) 7.2.1 RB SPRAY 1102-14 (D) 7.2.2 INITIATE, MAKE AND COWLETE A RB PURGE (P) OR (S) (1102-14) 7.3 PENETRATION fRESSURIZATION (1) 7.3.1 PENETRATION COOLING SYSTEM 1104-16 (D) 7.3.2 PENETRATION PRESSURIZATION 1104-21 (D) 7.4 REACTOR BUILDING - HVAC (1) 7.4.1 RB RECIRCULATION 1104-14D (D) 7.4.2 REACTOR C0WARTENT SYSTEM 1104-14C (D) 7.4.3 STEAM GEN.C0WARTENT SYSTEM 1104-14A (D) 7.4.4 OPERATING FLOOR VENTILATION SYSTEM 1104-148 (D) 7.5 AUXILIARY & FUEL HANDLING-HVAC (1)
- 7. 5.1 AUX. & FH BUILDING SUPPLY AND EXHAUST '
1104-15A (D) 7.5.2 SPENT FUEL PUW AREA y
E 1104-15B (S) 9 7.5.3 NSCC AND DECAY HEAT
/
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E NucI m k W J M Q Pl Number S211.,os_2s11.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM g-gg APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 7.0 BUILDING SUPPORT SYSTEMS CONTINUED TASK EXAMINER DATE
- 7.6 CONTROL BUILDING AND CONTROL ROOM HVAC (1)
- 7. 6.1 CONTROL ROOM HVAC 1203-24 (D) 7.6.2 CONTROL BUILDING VENTILATION SYSTEM 1104-15 (D) 7.7 SERVICE BUILDING - HVAC (1) 7.7.1 SERVICE BUILDING 1104-24D (D) 7.8 REACTOR BUILDING NORMAL COOLING (1) 7.9 FIRE PROTECTION SYSTEM (1) 7.9.1 FIRE SERVICE WATER SYSTEM 1104-458 (D) 7.9.2 FIRE SERVICE SPRINKLER SYSTEM 1104-45C (D) 7.9.3 FIRE SERVICE DELUGE SYSTEM 1104-45D (D) 7.9.4 WALK THROUGH YOUR RESPONSE TO FIRE ALARM l
ANNUNICATORS l
7.10 DIESEL GENERATOR BUILDING - HVAC i
(1)
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7.10.1 DIESEL GENERATOR BUILDING 1104-24M (S)
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8.0 REACTOR MANIPULATIONS TASK EXAMINER DATE 8.1 REACTIVITY CALCULATIONS 8.1.1 SHUIDOWN AND OPERATING REACTIVITY BALANCE 1103-15 (P) 8.1.2 BORON CHANGE REACTIVITY BALANCE 1103-15 (P) 8.1.3 SHUTDOW MARGIN CALCULATION 1103-15 (P) 8.1.4 XENON POWER BLOCK 1103-15 (P) 8.2 REACTIVITY CHANGES THE TRAINEE DURING HIS ON-THE-J08 TRAINING PHASE WILL PERFORM AT LEAST FIVE (5) REACTIVITY CHANGES AS DESCRIBED BELOW, WITH NO MORE THAN FOUR (4) BEING ANY COMBINATION OF ITEMS 2 AND 5.
REACTIVITY CHANGES WILL BE DOCUENTED ON THIS SHEET 8.2.1 CRITICAL APPROACH FROM SUBCRITICAL ON ' SOURCE RANGE INSTRUENTATION TO CRITICAL AT THE POINT OF ADDING HEAT ON THE INTERMEDIATE RANGE INSTRUENTATION.
8.2.2 ANY POWER LEVEL CHANGE (INCREASE OR DECREASE) 0F 10 PERCENT OF RATED
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POWER OR GREATER WITH CONTROL RODS IN MANUAL 8.2.3 REACTOR SHUTDOWN FROM CRITICAL AT 15 PERCENT OF RATED TO SUBCRITICAL E
SHUTDOWN ON SOURCE 9
RANGE INSTRUENTATION o
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DURING CRITICAL g
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Revision No.
TMI-l DIRECT SENIOR REACTOR OPERATOR TRAINING PR0rJAM n n APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 8.0 REACTOR MANIPULATIONS CONTINUED TASK EXAMINER DATE 8.2 REACTIVITY CHANGES CONTINUED 8.2.5 OPERATION OF REFUELING BRIDGE TO CHANGE CORE GE0ETRY DURING REFUELING 8.3 CORE POWER 8.3.1 MONITOR AND CALCULATE QUADRANT POWER TILT 1203-7 (P) 8.3.2 MONITOR AND CALCULATE CORE IMBALANCE 1203-7(P) '
INAL VERIFICATION:
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TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 0-00 APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 9.0 SITE EMERGENCIES
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TASK EXAMINER DATE 9.1 PLANT RESPONSE TO PENETRATION OF PROTECTED AREA 1202-13 (D) 9.2 FIRE 1202-31 (D) 9.3 FLOOD 1202-32 (D) 9.4 EARTHQUAKE 1202-30 (D)
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APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 10.0 DEMONSTRATE THE USE OF THE PLANT C0ffuTER FOR:
TASK EXAMINER DATE 10.1 LEAXAGE CALCULATIONS (P) 1 10.2 SAXON PROGRAM ACCESS (P) 10.3 CHANGING TREND RECORDER POINTS (P) 10.4 FINDING ALARM POINTS (P) 10.5 DISPLAY AND PRINTOUT OF YARIOUS GROUPS (P) 10.6 OPERATOR TREND GROUPS (P) 10.3 CHANGING TREND RECORDER POINTS (P) 10.4 FINDING ALARM POINTS (P)
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TMI-1 DIRECT SENIOR REACTOR OPERATOR TPAINING PROGRAM '
n on APPENDIX "B" LICENSED OPERATOR OJT CHECKLIST 11.0 DEMONSTRATE THE USE OF THE PLANT C0WUTER FOR:
i TASK EXAMINER DATE 11.1 C00LDOWN OUSIDE CONTROL ROOM 1202-37 (D) 11.2 PLANT STARTUP 1102-2 AND 1103-8 (D) 11.3 PLANT SHUTDOWN 1102-10 (D) 11.4 PLANT C00LDOWN 1102-11 (D) 11.5 PLANT HEATUP TO 525* 1102-1 (D) -
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APPENDIX "C" DIRECT SR0 - PROCEDURE QUALIFICATION ADMINISTRATIVE PROCEDURES READ AND DISCUSS THE FOLLOWING ADMINISTRATIVE PROCEDURES.
NAME:
PROCEDURE QUAL SIGNATURE DATE 1.
DOCUMINT CONTROL 1001 (1) 2.
Procedure Revisions and Approval 1001 A (1) 3.
Procedure Preparation 1001D (1) 4.
Procedum Utilizatfor.1001G (1) 5.
Periodic Review of Procedures 1001K (1 )
6.
Station Onganization and Chain of Comand 1009 (1) 7.
Technical Specifications Surveillance Program 1010 (1)
B.
Controlled Key Locker Control 1011 (1) 9.
Equipment Control (Locking)
AP 1001 (1)
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'11. Equipment Control (Tagging)
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NAME:
PROCEDURE QUAL SIGNATURE DATE 9.
SHIFT RELIEF AND LOG ENTRIES 1012 (1)
- 10. BYPASS AND SAFETY FUNCTIONS AND JUlfER CONTROL 1013 (1)
- 11. CORRECTIVE MINTENANCE AND MACHINERY HISTORY 1026 (1)
- 12. PREVENTIVE MINTENANCE 1027 (1)
- 13. OPERATOR AT THE CONTROLS 1028 (1)
- 14. CONDUCT OF OPERATIONS 1029 (1)
- 15. NUCLEAR PLANT STAFF WOPXING HOURS 1031 (1)
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i NAME:
PROCEDURE QUAL SIGNATURE DATE
- 17. INSTRUENTS OUT-0F-SERVICE CONTROL 1036 (1)
- 18. CONTROL OF CAUTION AND DNO TAGS 1037 (1)
- 19. EVENT REVIEW AND REPORTING REQUIREMENTS 1044
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CODE QUAL SIGNATURE (1)
DATE 1.
NOTICES, INSTRUCTIONS AND TO WORKERS: INSPECTION 10 CFR 19 (2) 2.
STANDARDS FOR PROTECTION AGAINST RADIATION 10 CFR 20 (2) 3.
REPORTS OF DEFECTS AND NON-COWLIANCE 10 CFR 21
.(2) 4.
DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES 10 CFR 50 (2) 5.
OPERATORS' LICENSE 10 CFR 55 (2) 5.
PHYSICAL PROTECTION OF PLANTS AND MATERIALS 10 CFR 73 (2) 7.
REACTOR SITE CRITERIA 10 CFR 100 (2)
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APPENDIX F: NON LICER5ED OPERATOR CHECKLIST O
h TMI-I SECil0N : SECONDARY m
m-2" gaE:
SOCI AL SEtt*.ITV NtMBER:
o DIPLOYEE ! AMBER:
N q
NLMBER PROCEDURE TASK TASK EXAMINER SIG.
DATE HOURS M
31 kack Out And Rock In 4160 Volt Ork 9
()
n 32 1106-2 Place 8th Stags Heating On Line
-4@
33 1106-8 Purge Generator With CD-2 O
h 1
34 1106-8 F!Il Generator with H.
2 rn 6
g L
35 1106-8 Fill Generator With I.A.
o 36 1106-10 Place Gland Seal Steam In Operation T2;
-4
'?
JT 1106-4 Place an Aun Boller In Service o
J8 1104-9 AJ ust Circ Water Blowdown
- z J
Q 3g 1303-4.16 An Emergency Diesel Generatur In E.5. St/Sy cn 3=
y to 1303-4.16 Perform Emergency Diesel Run Surveillance 41 Place Turbine Bypass EF-V-30A/B Valve In Manual Auto l
42 1300-3F A/B Test Run EF-P-2 A/B 43 1300-3G A/8 Test Run EF-P-1 44 Rdgs. Sheet Cosplete Secondary Readings 4
3 c,
I rs TCIAL HOURS IHl$ PAGE C
3 if SE o
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ADMINISTRATIVE MANUAL 6211-ADM-2611.03 f -
Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAf MTMf: Do ne_cau a ne APPENDIX "G" WATCHSTANDING CHECKLIST PERFORM THE FOLLOWING EYOLUTIONS AND ATTACH COWLETED READING SHEETS CANDIDATES SIGNATURE UPON COWLETION 1.
TAKE A0 OUTBUILDING READINGS FOR ALL SHIFTS (7-3)
(3-11 )
(11 -7 )
2.
TAKE A0 PRIMARY PLANT READINGS FOR ALL SHIFTS (7-3)
(3-11 )
(11 -7 )
3.
TAKE A0 SECONDARY PLANT READINGS FOR ALL SHIFTS (7-3)
(3-11)
(11 -7) 4.
TAKE CR0 READINGS FOR ALL SHIFTS (7-3)
(3-11 )
(11-7) l l
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A000105011 82 50.0
Number 6211-ADM-2511.03 Title Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM n_nn APPENDIX "H" ORAL EXAM
SUMMARY
SHEET CONTINUED CANDIDATE:
EXAMINER:
DATE:
FURTHER ACTION REQUIRED (IF NONE, SO STATED)
REVIEWED BY:
51GNAluRE OF EXAMINER
- SUPV.,LICEN5tD OPER. TRNG.
- FORWARD C0!fLETED SUlHARY TO SUPERVISOR, LICENSED OPERATOR TRAINING.
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Number h
6211-ADM-2611.03!,
Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PQorMM n nn APPENDIX "I" SHIFT FOREMAN TRAINEE DUTIES CHECKLIST SIGNATURE (SF/SS) 1.
CONDUCT SHIFT RELIEF AS A SHIFT FOREMAN 2.
MAKE A LEFT HAND LOG ENTRY IN ACCORDANCE WITH AP 1012 3.
REVIEW ONE COWLETE SET OF OPERATOR READING SHEETS 4.
DEMONSTRATE PROPER HANDLING OF A CHEMICAL DEVIATION SHEET 5.
DEMONSTRATE PROPER HANDLING OF TECH SPEC SURVEILLANCE DATA AND SCHEDULES.
6.
DEMONSTRATE PROPER HANDLING OF OPS SURVEILLANCE DATA AND SCHEDULING 7.
DEMONSTRATE PROPER HANDLING OF ISI DATA IN THE ALERT RANGE B.
DEMONSTRATE CORRECT HANDLING OF WORX REQUEST (C0WLETION/ INITIATION) 9.
DEMONSTRATE PROPER HANDLING OF QA HOLD POINT STAW
- 10. MAKE THE PROPER LOG AND CHECKLIST ENTRIES NECESSARY TO COWLETE A VALVE LINEUP CHANGE WITHOUT A TCN.
11. AUDIT THE TCN AND STP BOOKS
'13.
DEMONSTRATE KNOWLEDGE OF ALL COMMJNICATION SYSTEMS INCLUDING NRC PHONES NAWAS LINES, AND EMERGENCY PLANNING PHONED I4. DEMONSTRATE PROPER METHOD OF RECALL OF FLANT PERSONNEL E
INCLUDING USE OF RECORD-A-PHONE n
[ 5.
PROPERLY APPROVE AND DISCUSS TESTING REQUIREMENTS FOR g
ESAS COMPONENT TAG OUTS.
h 6.
CONDUCT A CREW TURNOVER BRIEFING 7.
DENONSTRATE KNOWLEDGE OF DUTIES OF MEMBERS ON THE FIRE BRIGADE A000105011 52 53.0
ENuclegogj{gl;% E pPY "C;
^
.Aos.2e11.03 Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PROGRAM 040 APPENDIX "J" DESIGNATION OF FOREMAN AS FINAL OJT EXAMINER DATE:
are hereby designated to serve as 5 HIP I SHIFT FOREMAN the final verification examiner for Replacement SRO's on Shift for DJT LETTER sections noted below:
List Sections:
SHIF I
, Silt i 5 UPtRV 150 R cc: Operator Training Section I
2 m
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6211-ADM-2611.03 Revision No.
TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAINING PRnrsRAM n_ _n n APPENDIX "K" SIMJLATOR TRAINING A nuclear plant simulator provides a means of training individuals to contml the plant during routine conditions and to cope with nuclear plant transients and accidents.
This training should prepare the candidate to supervise proficiently rVutine evolutions and carryout abnormal / emergency actions for the contml room. Candidates shall practice manipulating the controls of an applicable simulator as described in reference 5.6.
A., a minimum th license candidate shall participate in training sessions that include those listed below. The use of a simulator for perfomance of reactivity manipulations addressed in this program is authorized.
The following control manipulations and plant evolutions are required: Those control manipulations which cannot be performed at the plant shall be performed on a simulator.
(1)
Plant or reactor startups to' include a range that reactivity feedback from nuclear heat addition is noticable and heatup rate is established.
(2)
Plant shutdown.
(3)
Manual contrV1 of steam generators or feedwater, or both, during startup and shutdown.
(4)
Any significant (10 perreat) power changes due to manual changes in control rod position or recirt:ulation flow.
(5)
Loss of coolant including:
(a)
Significant steam generator tube leaks (b)
Inside and outside primary containment (c)
La rge and small, including leak determination (d)
Saturated reactor coolant response (6)
Loss of core coolant flow / natural circulation.
(7)
Loss of all feedwater (normal and emergency).
(8)
Boration or dilution, or both during power operation.
t (9)
Any reactor power change of 10 percent or greater where load change is performed with load limit control.
l (10) Loss of instrwent air (if simulated plant specific).
(11) Loss of electrical poster (or degraded power sources, or both)
(12) Loss of condenser vacuum.
5 (13) Loss of service water if required for safety.
(14) Loss of shutdown cooling.
5 (15) Loss of component cooling system or cooling to an individual 5
component.
E (16) Loss of protective system channel.
7 (17) Mispositioned control rod or rods (or rod drops) l (18) Inability to drive contrV1 rod g
(19) Condition requiring use of emergency boration or standby liquid E
contrV1 system.
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A000105011 52 55.0
"^ I.
ENuziegog ggglZgpPY Number e211.A0s.2e11.03 Revision No.
Title TMI-1 DIRECT SENIOR REACTOR OPERATOR TRAIMfWn DD0GDAM O_O O (20) Fuel cladding failum or high activity in reactor coolant of off gas.
(21) Turbine or generator trip.
(22) Loss of nonnal feedwater or nonnal feedwater system failure.
(23) Malfunction of automatic control system (s) which affect reactivity.
(24) Malfunction of mactor coolant pmssum/ volume control system.
(25) Reactor trip.
(26) Main steam line bmak (inside or outside containment).
(27) Nuclear instrument failum(s).
Participation at simulators shall be in groups of no mom than four (4) people manipulating the controls or dimeting the activities of individuals during plant exert:ises.
An examination using the simulator shall be conducted while at operating power with plant malfunctions and while starting up the reactor, The certification examination shall demonstrate the candidates ability to:
(1)
Manipulate the controls in a, safe and competent manner.
(2)
Predict instrument response and use instrumentation available.
(3)
Follow the facility procedures.
(4)
Recognize significance of alanns and annunicators, diagnose the problems they represent, and mspond with appropriate actions.
(5)
Communicate properly and effectively.
4 startup certification is mquimd by each candidate who has not previously
- ompleted one for Unit 1.
The use of the simulator for this requirecent is iutho r' zed.
e 9
5 N
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,4 LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM DESCRIPTION 4
TMI - 1 Submitted:
/7, f/
S. L. Newton DATE Operator Training Manager
.s Approved:
U
/7 Ny R. A. Knief Date Manager, Plant Training l
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1 Approved:
m / 7, jfd*
s M. J. Ao a Date Manager of Operations I
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a TABLE OF CONTENTS i
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1.0 Purpose....................................................
1.0 2.0 Reference..................................................
2.0 3.0 Definitions................................................
3.0 4.0 Program Description 4.1 0bjectives...............................
4.0 4.2 Pre-PiraAed Lecture Series........................... 5.0 l
4.3 skills Training D a1uation..........................
19.0
'Tj 4.4 operational Review Progrant.................-......... 34.0
~
~
4.5 Annual Requalification..............................
37.0 Special Re train'ing Programs.......................... '45. 0 4.6
~
4.7 Requalification Program D a1uation..................
51.0 4.8 Responsibilities....................................
53.0 4.9 Requalification Program Records.....................
59.0 4.10 Program Approva1.............................'.......
60.0 Appendices A.
Off Shift Licensed Operator Watch Standing Documentation A.1
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1.0 PURPOSE The goal of the operator requalification program is to enhance nuclear plant safety and reliability by maintaining a bigo level'of skill and knowledge in licensed senior operators and licensed operators.
To achieve this goal, the operator requalification program is desig'ned to be sufficiently broad in scope to review areas of knowledge necessary for safe plant operation and flexible enough to
, cover recent operatius experience and operational changes so that proficiency can be enhanced and operational safety maintained.
7 The requalification prooram described in this document is 5.~. Q
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- - -' implemented utilising four interrelated segments. These segments ares 1)
Pre-Planned Lecture Series
- 2) sk12J s Training and Evaluation
- 3) Operational Review Program
- 4) Annual Examiriation at i Evaluation Each program segment is described separately. The operator requalification program shall be conducted on a cyclic basis so that all program requirements are comp 1sted in a period not to exceed two years.
1.0
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A Successive requalification programs shall be conducted.on a schedule enabling a continuing program to exist.
The operator requalification program shall be e'stablished with fixad performance standards and specified remedial training requiraments in the event of deficiencies occurring. The program training materials, performance results and records aball be maintained in a fully auditable manner.
i Guidelines pei.aining to duration of training in tb6 requalification program are estimates of the ' time needed for retraining of licensed personnel. The training sessions needed to cover special nLclear plant operating situations or significant nuclear industry operating experiences may result in adjustments to these estimates. The duration of training shall also be adjusted as appropriate in order to assure that licensed personnel 1
performance meets or exceeds established performance standards.
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- 0-REFFRENCES a) 10 CFR 55, Appendix h, Draft Revision 5/14/80 t
b)
NRR letter of March 28, 1980 on Qualifications of Reactor Operators t
c) NUREG 0737, Enclosure 3 d)
ANE 3.1, Draft Revision 10/80 e
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Reg. Guide 1.8, Draft Revision 9/80 f)
INPO-Nuclear Power Plant Requalification Program of Licensed Personnel 3.0 DEFINITIONS The definitions given below are of a restricted nature for the purpose of tais progres.
I Drill - A supervised training exercise conducted in a work environment for the purpose of developing and maintaining skills tequired to cope with plant abnorma5/ emergency conditions and including an evaluation of performance.
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contact sour of Instruction - A one bour po'riod in which the course instructor is present or insediately available for instructing or assisting students: 1ectures, seminars, discussions, problem solving sessions, and examinations are considered contact per ods under this definition.
Licensed operator (RO)
Any individual who possesses an operator's license pursuant to Title 10, Code of Federal Regulatior.s, Part 55,
" Operators' Licenses'.
Licensed Senior Operator (SRO) - Any individual wno possesses a
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j senior operator's license pursuant to Title 10, Code of Federal Regulations, Part $5, " Operators' Licenses".
Annual - As referred to in the operator requalification program, is twelve (12) months, not to exceed fif ceen (15) months, in order to acccmodate plant operations. March 1, and subsequent anniversaries of tais date, will De considered the starting date of each annual cycle of requalification program operation.
Shall, should, and May - The word "aball" is used to denota a requirement; tne word "snould" to denote a recommendations and the j
word "may" to denote permission - neither a requirement nor a
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4.0 PROGRAM DESCRIPTIOtt 4.1
, OBJECTIVES n o Requalification Program objectives are to:
- 1) Maintain nuclear plant operational safety and reliability.
- 2) Assure that licensed personnel maintain the high level of skill and knowledge required to accomplish routine and emergency duties.
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- 3) Establish a system for evaluating and documenting licensed personnel proficiency and competency.
4.2 PRE-PLANNED LECTURE SERIES The operator raqualification program aball include pre-planned training sessions conducted on a regular and continuing basis. The training sessions aball include two types of lecture series as follows:
- 1) Fundamentals Review Lecture series 4
- 2) Operational Proficiency Iacture Series
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4.2.1 Fundamental:., Review Lecture Series The Fundamentals Xaview tTaining sessions cover areas l
in which the knowledge required of a licensed individual is relatively constant.
4.2.1.1 Lecturg series Moics The Fundamentals Review lecture topics are selected on an as-needed basis and aball include the following:
- 1) Theory and Pririciples of Reactor Operation.
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Heat Transfer, Fluid Flow and Tnermodynamics.
- 3) Features of Facility Design including Plant Systems.
- 4) Gereral and Specific Plant Operating Characteristics including Expected Response to Equipment Failure.
- 5) Plant Instrumentation and Control Systems.
- 6) Plant Protection Systems.
- 7) Engineered Safety Systems.
- 8) Badiation Control and Safety and Plant O.B Chemistry.
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- 9) Applicable Portions of Title 10, Chapter I, Code of Federal Regulations.
- 10) Fuel Bandling and Cor.e Parameters 4.2.1.2 Lecture Series Epic Selection The tepics presented in the Fundamentals Revien series should reflect the general rec. tits of the annual examinations and performance of the licensed personnel as evaluated by'the Manager of Operations and the Operations and Maintenance Director.
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The scope of the lecture series should be determined by the Supervisor, Licensed Operator Training and approved by the operator Training Manager. The depth of coverage in each topic'should reflect typical deficiencies identified by the annual examinations.
4.2.2 Operational Proficiency Lecture Series he Operational Proficiency training sessions cover I areas which involve essentfal plant operational guidelines.
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A 4.2.2.1 Lecture Series Topics The Operational Proficiency lecture topics are selected to ensure coverage of essential plant operational guidelines and to ens'ure operational changes and experiences are integrated into licensed individual's training. The lecture topics should include the following:
1)
Normal, Abnormal and Emergency Operating Procedures and Changes mereto.
2)
Tecnnical Specifications.
- 3) Administrative Procedures, Conditions 7.0 ev,,. - -. -,.
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n and Limitations and Changes Thereto.
- 4) Major Operational Evolutions.
- 5) Facility Design and License Changes.
- 6) Operating History'and Problems.
- 7) Related Nuclear Industrf Operating Experience.
- 8) Mitigation of Accidents Involving a Degraded Core.
4.2.2.2 Lacture Series Tepic Selection The topics presented in the Operational
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Pepficienc[(seriesaballincludeallthe top,1cs listed in Section 4.2.2.1, unless 4..
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the applicable information is covered in another appropriate manner, such as staff discussion sessions or Operational Review Program (Section 4.4) discussion sessions.
The scope of the lecture series should be r.etermined by the Supervisor, Licensed Operator Training and the Operator Training Manager taking into account the Manager of Operation's and the Operations and Maintenance Director's inputs. The depth of the coverage in esca topic snould 8.0
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reflect the knowledge required of the Licensed Senior Operator 4.2.3 Pre-Planned Lecture Series Schedule The. Pre-planned Lecture Series aball be scheduled on an annual basis. Lectures may be deferred due to f
unanticipated events, but should be conducted as soon as practicaole thereafter and witnin the annual cycle.
The lecture series aball be held on a continuing basis with a weekly schedule of lectures designed to be repeat 6d for each shift when that shift is designated,for its training, week. ' The'progran and-senedule will be determined by unit operations or pecjected operations and must take into account planned and unplanned outages and available simulator i
time. It shall typically involve approximately 240 contact hours of instruction divided among the program topics and appropriately scheduled throughout the year. Records of the topics covered in each
_. session shall be maintained by the Training Department.
4.2.4 Pre-Planned Lecture Series Attendance Attendance of all licensed personnel shall be recorded. Absences abould be approved in advance ey 9.0
.O the Manager of Operations or the Operations and Maintenance Director, Unit 1, and should be limited to one training week per year. Additional absences unless approved by the Manager of Operations aball result in the individeal being removed from licensed duties and placed in an accelerated requalification program until such time as the missed material 'is made up.
In any case, the individual who misses training shall be responsible for the material presented in his, absence and shall take the quiz that was given on the missed material. Those personnel whose annual written examination scores indicate that D'
a mandatory upgrading of their knowledge level is required, as indicated by a grade of less tuan 804 in
. any section, must attend the applicable pre-planned lecture, series presentation. Mandatory attendance requirements shall be determined by the Supervisor, Licensed Operator Training.
4.2.5 Pre-Planned Lecture Series Training Methods The pre-planned lecture series shall use training sessions supported by prepared lesson plans.
4.2.5.1 Lecture Presentation Por each training session in the lecture v
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f" series, a lesson plan shall ce prepared, reviewed, and approved in accordance with Training Department Procedures TD 1103 and TD 1104.
I The incorporation of training aids such as trainee bandouts, films, slides, models, transparencies, and videotape presentations is encouraged. The lesson plan shall become the reference source for the information covered during the lecture and shall be retained as part of the.
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a In-the event that vidactape or film presentations or computer-based instruction are used, an instructor shall be available to embellish, explain or emphasize the presentation and to respond to any questions or comments from the trainees.
4.2.5.1 Study Periods Study periods should be scheduled in conjunction with the Pre-Planned Lecture Series to provide licensed trainees an 11.0 is-
/~s opportunity to reinforce the lecture series learning experience and to study new or additional materials. While individual self-study.is encouraged, it should not be substituted for training sessions implemented by an instructor conducted as part of the Pre-planned Zacture series.
4.2.5.3 Instructor Qualificatior.s 1.
Training Department and facility instructors who teach systems, integrated O.c.
i responses and transient c,urses_shall have, demonstri.ted their competence to the MRC
'bjf successful completion of a senior operator examination.
2.
' Guest" lecturers who are experts in a particular subject area.need not possess the above qualification. The scheduling and appearance of " Guest" lecturers shall be approved in writing by the Operator Training Manager or Manager, Plant Training.
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Training Department instructors should attend the first Instructor Development Program presented following their selection as instructors. Waivers may be approved by the Manager, Plant Training based on previous experience.
4.J.6 Pre-Planned Lecture Series Evaluation The lecture series aball be evaluated by conducting evaluations of the trainee's knowledge, effectiveness of the overall lecture series, and effectiveness of the instructors.
Cp 4.2.6.1 Lecture series Quiz
.After each week of lectures, all trainees shall take a written, closed-book quis covering the lecture topic (s).
4.2.6.1.1 Quis Administration During or at the completion of a group of lectures, an evaluation of trainee knowledge sball be made. The evaluation aball contain questions related to the 13.0
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lesson plan objectives covered during the lectures. All lecture topics covered during tne training session should be represented by question 6 in the evaluation. In addition, questions aball be included from selected abnormal and emergency procedures as designated by the Supervisor i
Licensed Operator Training, such that all abnormal and n.
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tested on a bia.inual basis.
A variety of question types may be used, but questions requiring analysis or detailed discussion s.bould predominate. An answer key
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with predetermined question point values should ce prepared for evaluation and record keeping purposes.
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!. - j-Operator Training Manager and Manager, PJant Training of the evaluatiori results and provide a recommendation regarding the trainee's removal from licensed duties and entrance into an accelerated requalification progran (Section 4.6.1). Trainees whose attendance at all or part of the training -sessions covered by a ._r particular quiz is mancatory based on tDe previous annual 16.0 'A swamination, but must achieve a score of at least 80% on the applicable sections of the first quiz or be assigned an accelerated requalification program per section 4.6.1. 4.2.5.2 Lecture Series Effectiveness The effectiveness of the lecture series should be evaluated by the trainees, Manager of Operations and the Supervisor, LiceTsed Operator Training. The results -A of this ev'aluation.should be factored into rb subsequent requalification training. -c. - - 4.2.5.2.1 Lecture Series Evaluation An overall evaluation of the annual lecture series should be conducted on at least an l annual basis. The evaluatic,n should encompass the instructors, training asterials, presentation techniques, quiz tecnniques, and classroom facilities. i 17.0 e ,y,,,,,y,,..,,._,,,,,_,,,_,,_y_ _ _,,,,_,,,.__.,_,m,_-. X - em. Sis evaluation should be conducted by individuals designated by the Supervisor, Licensed.Operatne Training and should consider input from the trainees, Manager of Operations and the program instructors. Significant problems should be considered and resolved by the Supervisor, Licensed Operator Training and the operator M. . f.,. Trainia_v.na.naser. ~ ~ 4'.~2.6.2.2 Presentation Evaluation Evaluation of selected lecture i series training sessions saall be conducted periodically. The evaluations should be directed toward ensuring overall quality of instruction for the lecture series. The evaluation should encompass instructor preparition, 1 presentation techniques, and .v. 18.0 A 4 technical content of the lecture. This evaluation should be conducted by personnel, designated by the Manager, Plant Training or the f ' Operator Training Manager. t Problems identified by these evaluations should be resolved by the instructor and,the Supervisor, Licensed Operator i.?.., Training. .u, -~ ~ o 4.3 SKILLS TRAINING AND EVALUATION 4 In ords-to maintain'an acceptable level of skills and familiacity associated with the nuclear plant systems,* controls, and operational procedures, each licensed individual shall participate in frequent and varied plant evolutions. Each licensed individual shall demonstrate i j operational proficiency by participating in the following 1 activities: 1) Reactivity Manipulations and Plant Evolutions 2) Nuclear Plant Simulator Exercises l
- 3) Plant Drill Prograa k
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To maintain these skills, licensed operators aball actually manipulate the controls while licensed senior operators may either manipulate or actively supervise manipulation of the controls. Training to achieve proficie.ncy should be planned so that skills training exercises are repeated until proficiency is demonstrated. 4.3.1 Reactivity Manipulations and Plant Evolutions During the two year term of the NRC license, each licensed individual shall participate in a variety of reactivity control manipulatio's and plant evolutions. n g 4.3.1.1., Normal Plant Evolutions 'T e.. .. : '.;=.-. - - ~. : i ~. ~ ~ ~ - = 2~ 2* - v' = U "".'. C~ " ~ on an annual basis,,eaca licensed individual shall participate in the following plant evolutions either at the nuclear plant or at a nuclear plant simulator
- 1) Plant or reactor startup and power escalation to a range where reactivity feedback from nuclear beat addition is noticeable and bestup rate is established.
- 2) Plant shutdown.
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- 3) Manual control of stea generator water level and/or feedwater flow during plant startup and/or shutdown.
4) Bo' ration and/or dilution during power operation.
- 5) Reactor power changes of Ibn or M
greater where rod control is in manual.
- 6) Reactor power changes of lot or 4.
greater where load change is performed w(tb load control on manual.
- 7). Operation of turbine controls in manual,during turbine startup.
- 8) " Decay beat removal system operation.
~ 9) Incore monitoring system'operetion.
- 10) control roca calculations including i
beat balance, coolant inventory balance, and reactivity balance. p Individual performance during these plant + evolutions shall be monitored and deficiencies corrected so that 1-satisfactory proficiency is desc,nstrated. 4.3.1.2 Abnormal /Deergency Plant Evolutions ' On an annual basis, each licenseo h., l 21.0 1 i ! ~.... M. individual shall participate in training exercises covering the following ' plant abnormal / emergency conditions either at a nuclear power plant s'imulator or during the plant drill program: 1) Re, actor trip
- 2) Turbine or generator trip 3)
Ioss of coolant including: a)* Significant steam generator leaks b) Significant pressurizer leaks c) Iarge and small leaks located f
- inside and outside primary
~% containment (ineluding leak rate "- - determination for small leaks h eide containment) d) Saturated reactor coolant system response
- 4) Ioss of coolant flow / natural circulation 5)
Ioss of all feedwater (normal and emergency)
- 6) control room inaccessibility
- 7) Ioss of shutdown cooling.
22.C ~. .~ On a two-year cyclic basis, each licensed individual shall participate in training exercises covering the following plant abnormal /energency' conditions either at a nuclear plant simulacor or during the plant drill program. 1) Nuclear instrumentation failure (s) 2) Loss of protective system channel (s)
- 3) Mispositioned control rod (s) (or rod drops)
- 4), Inability to drive control rods
- 5). Conditions requiring use of emergency
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.boration or standby liquid control -3_, ~ ~ system. 6) Fuel cladding failure or biga activity ' in reactor coolant or offgas
- 7) Malfunction of automatic control systes(s) which affect reactivity 8)
Malfunction of reactor coolant l pressure / volume control systes
- 9) Loss of instrument air
- 10) Loss of electrical power and/or degraded power sources
- 11) Ioss of condenser vacuum Se 23.0
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- 12) Loss of service water
- 13) Loss of component cooling system or cooling to an individual component
- 14) Loss of normal feedwater or normal I
feedwatet system failure
- 15) Main steam line break (inside or outside containment).
Besponse to abnormal /eaergency conditions should include use of alternate sethods of* l accomplishing a given function, suca as alternate methods of core cooling. -. :..u .:. -c - Exe'rcises.inv.ol.ving multiple, failur,es. and/or operator error shall be included. Utilisation of applicable plant procedures and tocanical specifications during the training exercises saould not be minimised. Individual and operational team performance during the abnormal / emergency training exercises shall be monitored and deficiencies corrected so tnat satisfactory proficiency is demonstrated. 4.3.1.3 Performance of Reactivity Manipulations and Plant Evolutions i Reactivity manipulations and plant ,,,n - - - ~ - - ~e-- ~, - - -
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et evolutions aball be conducted either at the nuclear plant or at a suitable nuclear plant simulator.
4.3.1.3.1 Performance of Normal Plant Dolutions Normal plant evolutions aball be either performed at the nuclear plant or performed at a suitable nuclear plant simulator (Section 4.3.2).
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4.3.1.3.2 Performance of Abnormal /
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Baergency Plant Wolutions Abnormal /eaergency plant i
evolutions shall be either performed at a nuc' er plant 4
simulator (Section 4.3.2) or
. conducted dering the plant r
drill program (Section 4.3.3).
i In the event that an actual abnormal / emergency condition occurs at the' plant and performance of tne licer. sed 1
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l personnel coping with the condition is satisfactory (as determined by the Manager of operations), credit for completion of a training exercise may be taken.
4.3.2 Nuclear Plant Simulator Exercises A nuclear plant simulator provides a means of training licensed individuals to conduct normal plant, evolutions and to cope with nuclear plant transient and accident conditions. Licensed individuals shall C
participate,in'a structured, train.ing program utilizing a nuclear plant simulator on an annual basis.
During the simulator training sessions, the tess concept should be utilised, emphasising individual roles in reporting, assignment of operational duties, use of plant procedures and use of technical specifications. Assignment to simulator training sessions which are direct interactions with the viuclear plant control panel should be made on a crew basis with otner licensed individuals integrated into p?
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I the crews not to exceed one additional individual per crew.
Each licensed individual shall complete nuclear plant simulator training sessions involving at least twenty (20) bours of direct interaction with the simulator nuclear plant control panel on an annual basis.
Brief post-evolution critiques conducted at the simulator nuclear plant control panels may oe considered as part of the direct interaction, gossion.
Lecture sessions conducted in conjunction with a
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in the Pre-planned Lecture Series'may be credited toward fulfilling the requirements of Section 4.2.
Reactivity manipulations, plant evolutions, and exercises which should be considered in the simulator training program include:
- 1) Moraal Plant Evolutions (Section 4.3.1.1).
2)
Abnormal / Emergency Plant Evolutions (Section 4.3.1.2).
- 3) Verification of Plant Operating Procedure Adequacy j
- 4) Demonstration of piant response to conditions l
identified from nuclear industry operating r.
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Instructors presenting simulator training sessions soall have demonstrated their competence to the NRC by successful completion of a Senior Operator Examination.
4.3.3 Plant Drill Program Plant drills provide a means of training licensed in'ividuals in responding to plant ainorme1/eaergency d
conditions.
Licensed individuals shall participate in the plant drill program on an annual basis.
4.3.3.1 Plant Drills Un an annual basis each licensed individual aball participate in plant drills. Plant drills anall be conducted so that each licensed individual actively participates in drills covering 1
abnormal / emergency plant evolutions (Section 4.3.1.2) whica are not adequately covered in the nuclear plant' simulator training program (Section 4.3.2).
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A Participation in a plant drill involves either responding,to drill conditions or being an assigned monitor for i.
observing / evaluating response to a drill.
Plant drills may be structured to review or carry out actions required to respond to abnormal / emergency plant conditions.
Plant drills may be conducted with the apprc, val of the Manager of Operations, on an. individual or team basis and asy involve:
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- 1) *Aeviewing plant proceduro steps.
2)
Identifying actions required to estaelian stacle plant conditions.
3)
Identifying equipment control locations and functions.
4)
Identifying expected plant instrumentation and alara response.
- 5) Reviewing.ccamunications necessary to gather information or coordinate team actions.
6)
Identifying supplementary actions aimed at mitigating results or causes of plant abnormal / emergency conditions.
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!A 4.3.3.2 Plant Detil Scenarios Each plant drill must be carefully planned arid monitored in order to ensure actual annormal/eaergency conditions are not inadvertently initiated during the drill and in order to evaluate individual or team response to the drill conditions.
Each plant drill structured to include carrying out ac*.lons should be planned in I
a prepared drill scenario, approved by the Manager'EfOperations. The Operations and W
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Maintenance Director and Director TMI-1
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.shall approve scenerios for major emergency drills. The drill scenario should include the following:
- 1) Purpose / objectives of the drill 2)
Initial conditions
- 3) General description
- 4) Nethod of initiation
- 5) Precautions and limitations 4
- 6) Sequence of expected actions i
- 7) Point of termination / conditions under whica the drill is to be secured
- 8) Final conditions
- 9) Monitors required / location s,_
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The drill performance should be evaluated and deficiencies identified. A drill critique should be held by the Senior m itor with the delli participants.
Deficiencies identified should be reviewed by tae supervisor, Licensed operator Training. Additions or modifications to training programs required to correct performance deficiencies should be initiated by the supervisor, Licensed Operator Training and/or the Manager of Operations.
27 4.3.d' ~~ Skills Eva'lua don Notes Licensed personnel performan.co and competency related -
to performing licensed duties shall be periodically evaluated. Repeated errors or other indicators of l
degraded proficiency should be reviewed by the Manager of Operations and the Operator Training Manager and appropriate training initiated.
i Evaluation of licensed personnel job performance should be utilised to relate job performance to regualification training. The Manager of operations should provide the Supervisor, Licensed Operator
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qn Training or the operator Training Manager with periodic observations identifying joo performance results related to requalification training.
Each licensed individual's performance shall be 4
evaluated during the following situations:
j 1)
Nuclear Plant simulator exercises
- 2) Plant drills The Supervisor, Licensed operator Training should ensure evaluations are conducted during the simulator and drill esercises.
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I 4.3.5 Ms Trainine Participation a u
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In the event that skills training guidelines for participation in normal plant evolutions (section 4.3.1.1), abnormal /eaergency plant evolutions (Section 4.3.1.2) or plant drills (section 4.3.3.1) are not met, exercises which will fulfill the l
requirements obould be scheduled and completed within twelve (12) weeks of the required period. If the requireaents are not completed within the twelve (12) week period, the Supervisor, Licensed Operator Training shall notify plant management and the Director TMI-I via the operator Training Manager and the Manager, Plant Training and provide a i
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recommendation regarding the licensed individual's removal from licensed duties.
In addition to meeting the requirements for participation noted above, off shift licensed personnel assigned to the operations Department shall actively participate in control roca operation a sinimum of one shift per month. Licensed instructors from the Training Department staff shall actively i
participate in control room operation a minimum of two stifta per month. During tais period these g
licensed pe,rsonnel must assume (actual or under Y
.., instruction,).' nd. perform,the duties;.of 'the.6n ehif t....'. 5 $ m n a
licensed operator as indicated by ocapleting Appendix A and forwarding to the Training Department.
l Based on sonedule constraints, satisfactory participation small be defined as meeting the requirements on a guarterly basis.
If an individual has not spent six shifts in the control room over a given quarter, he small have one month in which to l
make up the missed shifts. Failure to do so shall l
result in his being placed in the Inactive status Retraining program, Section 4.6.2.
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4.4 OPERATIONAL REVIEW PROGRAM The operational review program provides a system for on-shift review of selected operational experiences and changes to existing operating guidance or equipment. The operational review program enables continuing updating of on-shift personnel and establishes a means of disseminating new or changing information on a short term basis.
4.4.1 Modification Review
& continuing system aball be established by tne Manager of Operations so licensed individuals review documented, plant design changes, equipment Mr,,,.
, modifications. procedura changes aed technical-specification changes. Selected changes and modifications should be analysed and information pertinent to tne basis for the changes and their operational implications collected. This information should be formally transmitted to all licensed individuals with acknowledgement of review required.
Changes to emergency procedures, technical specifications and safety related systems aball be reviewed prior to the licensee assuming saift operation resp 6nsibilities.
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23 Mantg:r cf Operatiin3 cod taa Supervisor, Licensed operator Training should specify changes and modifications to be analysed, with information for review transmitted in accordance with the urgency of the situation. De Manager of Operations should ensure that all on-shift licens'ed personnel review the selected information in a timely manner.
mapanded coverage of plant design changes, equipment modifications, procedure caanges and technical
' specification changes in the operational Proficiency lecture Series (Section 4.2.2) saould be considered by the Supervisor, Licensed Operator Training.
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i' on-shift supervisory (Sao) personnel should provide i
i guidance'ta on-obift operators in interpreting and reviewing changes and modifications. An on-shift discussion period to review changes and modifications is encouraged.
f 4.4.2 Coeratine Deperience Review l
A continuing system shall be established by tee Manager of Operations so licensed individuals review
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operating experience feca TMI and from applicable j
segments of the nuclear industry. Selected operational events and reportable occurrences at the 4
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facility should be analysed and information pertinent to the event collected. Selected operational information from the nuclear industry snould be i
analysed. The following sources of information shall be considered:
- 1) Licensee Event Reports
- 2) Audit, evaluation, and inspection reports 3)
Publications and periodicals covering nuclear industry information.
4)
MSAC/INPO Significant Event Reports t
This information obculd be formally transmitted to all licensed individuals wita required acknowledgement of review. pe Manager of operations should e sure that all on-obift licensed personnel review the information in a timely manner.
5tchnical p nctions perso'nnel assigned to assess plant operating experience and the Supervisor, Licensed Operator Training shall specify operating experience to be analysed for training purposes, with information transmitted to all licensed personnel for review. Subsequent coverage of operating experience j
in the operational Proficiency Lecture Series l
(Section 4.2.2)should be considered by the Supervisor,
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Licensed Operator Training. Selected nuclear plant accident / transient situations aball be analysed and integrated into the Nuclear Plant Simulator Exercises (section 4.3.2) or the Plant Drill Prcgram (Section 4.3.3).
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ANNUAL REQUALIFICATION EXAMINATION In order to determine each licensed individual's knowledge of topics covered in the regualification program and provide a basis for determining areas in which retraining is needed, an annual requalification examination shall be given. The annual examination shall be given to all licensed individuals prior to the ocapie' tion of e'ach ' annual requalification
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program cycle and shall* consist'of an oral examination and'a written examination,.
4.5.1 Annual Written Examination An annual written examination shall be administered to all licensed individuals.
4 5.1.1 Written Examination Content no written examination aball contain examination questione covering the 37.0 e
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following topics:-
1)
Theory and Principles of Reactor operation 2)
Beat Transfer,. Fluid Flow and Thermodynamics 3)
Peatures of Facility Design 4)
General and Specific Plant Operating Characteristics
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plant Instrumentation and control Systems 4),
Plant Protection System 7)
Engineered ~ Safety Systems e.:,
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Applicable portions of Title 10, Chapter I, code of Federal Regulations
- 10) Fuel Bandling and Core Parameters
- 11) moraal, Abnormel and Energency Operating Frocedures
- 12) Technical Specifications
- 13) Administrative Procedures, Conditions and Limitations
- 14) Nuclear Industry Operating Experience The topics shall be grouped into at least six (6) examination categories for L.'
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n, evaluation purposes. The examination shall be structured so that the level of questioning is consistent with the individual's license level (no or smo).
4 5.1.2 Written Examination Administration The written examination should be prepared under a structure enabling consistency of questioning and minimizing possible compromise of examinations prior to administration. The following guidelines O
should be considered:
~1), An osanim tion question file shall be E.
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asemabled taining questions and anesers on each esamination topic.
- 2) Questions should be formulated from aany sources including a)
Licensed personnel training program.
b)
Requalification programs 1,
c) Plant documents such as i
technical specifications
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and procedures.
d)
Previous examinations.
e) Manager of Operations.
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f) operating experience.
g) plant design changes and system modifications.
3) no emanination should include a variety of question types, but' questions requiring analysis and/or I
explanation should predominate.
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- 4) Questions and answers should be l
l reviewed and approved by the
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Supervisor, Licensed operator Training prior to use.
- 3) ne supervisor, Licensed operator wg
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to update the emanination questions b
and answers file annually.
Personnel designated by the Supervisor, i
Licensed operator Training shall prepare l
the written examination (s) utilising the esamination question file. De number of l
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different examinations prepared should be consistent with preventing emanination ocapromise. The emanination may be administered in segments. The i
examination, answer key and grading system 1
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should be reviewed and approved by the Supervisor, Licensed operator Training, operator Training Manager, or Manager of operations prior to examination administration.
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The Supervisor, Licensed Operator Training shall designate qualified personnel to grade the written examination and shall review the graded esaminations for grading techniques and consistency.
4.5.1.3 Examination Performance Standards P.
A licensed individual receiving a grade of t,,
- 1ess than 700 in any emanination category or an overall grade of less than 404 shall be relieved of his license duties and placed in an accelerated qualification pecgram (Section 4.6.1L).
Under special circumstances waere a grade of less taan 704 bas been scored in a single section, the Director, TMI-1 any document the special circumstances and authorise an oral and written reexamination of the failed section within one (1) week.
If the oral exam is 41.0 o
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completed satisfactorily and a grade of 80% or greater is scored on tne written section, the individual may return t,o shift in a licensed status wit' the approval of the Director, TM2-1.
4.5.2 Ao_ntal oral Examinati m An annual oral emasination shall Le administered to all licensed individuals.
4.5.2.1 Oral Examination Content The oral esamination should contain quisetions oevering the following areaes
- 1) bloeweed'dutter and'responelbilities of the operating position oorresponding to the individual's License level.
2)
Actione in the event of abnormal conditione.
- 3) Actions in the event of emergency conditions.
4)
Interpretation of instrumentation responsee.
5)
Plant transient and accident response.
6)
Plant modifications.
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- 7) Procedure changes.
8)
Technical Specifications.
'9)
Energency Plan.
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- 10) Plant Operating history and problems.
- 11) Related nuclear industry operating experiences.
4.5.2.2 Oral Ibcamination Administration The oral examination sball be conducted under a structure enauling consistency of questioning and evaluation. The following O.
guidelines soould be considered.
1 5.I 1.). i checklis.t identiifing the areas to
,be covered aball be used.
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- 2) Overall ovaluation shall be made on a l
pass / fail basis.
- 3) Comments on individual strengths and I-weaknesses aball be made.
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Se Supervisor, Licen' sed operator Trainina
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and the Manager of Operations shall estaelish the oral examination schedule.
l Personnel assigned to conduct an oral evaluation shall be designated by the A
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Supervior, Licensed Operator Training and approved by the Manager of Operations.
Oral examinations shall be conducted by a Licensed Seniw Operator or personnel who have successfully completed education and training programs required for a senior operator's license. Each oral examin'ation should be structured so that an examination time of two (2) bours or more is appropriate.
The Oral espination sbould involve c.
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sessions conducted in the plant control
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room and in plant areas occupied by individuals whose actions are directed by the licensed operator.
4.5.2.3 Examination Performance Standards A failing overall oral examination grade
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shall require the licensed individual to s
be removed from his license duties and be
', ' placed in an accelerated requalification
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b 4.6 SPECIAL ItET'lAINING PROGRAMS Specific retraining programs for licensed individuals may be required to upgrade or refresh knowledge and skills related to licensed duties.
4.6.1 Accelerated Requalification Program The accelerai d requalification program is for licensed individuals having identified deficiencies requiring assignment to a special retraining effort.
4.5.1.1 Required Attendance Licensed individuals meeting one or more of the following criteria shall be assigned to an accelerated requalification program:
- 1) Annual requalification written saamination performance deficiencies per Section 4.5.1.3.
- 2) Annual requalification oral examination perioraance deficienciea Per Section 4.5.2.3.
- 3) Pre-planned lecture series quis performance deficiencies per Section i
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- 4) Significant licensed duty performance deficiencies identified by the Manager of Operations and/or the Supervisor, Licensed Operator. Training.
4.6.1.2 Program Content 2e accelerated requalification program 3
content aball be specifically structured to upgrade knowledge and skills identified as deficient. Examination categories and areas in which performance standards were not met aba'11 be covered in the program.
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2e. Supervisor, Licensed Operacor Training stiall De responsible for formulating individual accelerated requalification programs. Rey aball be approved by the Operator Training Manager and the Manager of Operations.
4.6.1.3 Program Administration i
n e accelerated requalification prograa 9
any involve a variety of training exercises including:
1)
Directed self-study.
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- 2) Oral interviaws and discussion sessions.
3)
Pre-planned lectures
- 4) Skills training exercises at the plant or utilizing a simulator.
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Personnel assigned to implement the i
training exercises shall be qualified in accordance with Section 4.2.5.3 or 4.3.2 as appropriate.
Program duration should be dictated by tae extent of tiraining required and. trainee's
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performance. -
4.6.1.4 Performance Standards successful completion of the accelerated requalification p ogram shall be determined by administering an examination. The examination shall cover l
all categories of the requalification
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written examination and/or all areas of l
the requalification oral examination originally failed. Se examination formit should be similar to the original l
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,av examination, and the examination shall be conducted by individuals designated by the Supervisor, Licensed Operator Training.
Performance standards for the accelerated requalification program shall be as follows:
- 1) A score of at least 80% on each accelerated requalification written examination category.
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- 2) A passing evaluation on the accelerated requalification oral Lo ezanination.
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In de event that these standards are not i
met, the individual's suitability for resuming iicensed duties will be reviewed i
by the Supervisor, Licensed operator Training. He shall provide a roccamendation to plant management and the Director TMI-1, via the Operator Training Manager and Manager, Plant Training regarding the individual's permanent removal from licensed duties or additional upgrading efforts to be considered.
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eA y.m If appropriate, another accelerated requalification program aball be structured to correct deficiencies.
4.6.2 Inactive Status Retraining If a licensed individual has not actively carried out licensed duties for a period in excess of four (4) sontas, a special retraining program and/or evaluation is required prior to resuming licensed duties.
Active status can be n'aintained by performance of h.
licensed dutie's atxi pdrticipation in the licensed s.*
personnel requalifica' tion
- pro' gram. Performance of licensed duties involves manipulation of oontrols whica directly affect reactivity or power level of the reactor or directing the licensed activitie's of licensed operators, and for those licensed individuals not normally assigned to an operating 4
shift, completing the requirements of Section 5.5 for participation in control roca operations.
In the event that a licensed individual does not maintain an active status, the Supervisor, Licensed Operator Training shall designate, subject to l
49.0
r approval of the Manager of Operations, a Licensed Senior Operator to conduct an oral examination similar in scope and format to an annual oral examination prior to resuming licensed duties. In
' addition, evaluation of performance in the current Pre-planned Lecture Series aball be conducted. If performance in the Pre-planned Lecture Series is unsatisfactory, a written examination similar in scope and format to the annual written examination
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(Section 4.5.1) shall be ' administered to the licensed individual prior to resuming licensed duties.
1 lh Consideration should ba given by the Manager of
' q Operations-to assigning the Iicerised"liidiiffdua'l' to a'
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training status on an operating abift prior to resuming licensed duties.
The performance standards applied to the annual requalification examination shall be used in evaluating the results of the oral and written
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examinations. If the performance standards are not met, the licensed individual shall complete an i
accelerated requalification program prior to resuming licensed duties.
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.Q Licensed duties may be resumed only upon certification of the Director TMI-1, which must be focwarded to the Nac.
4.6.3 Newly Licensed Individuals Newly licensed individuals aball enter the requalification program and participate in the annual program cycle upon receipt of their license. Newly licensed individuals successfully completing their NRC licensing examination less than three(3) months i
prior to an annual requalification examination may be
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excused from taking tbe current annual written and
!r-oral azaminations.
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4.7 REQUALIFICATION P'ROGRAM EVALUATIOil A requalification program review and evaluation shall be conducted on an annual basis by tho' Supervisor, Licensed l
Operator Training. The areas encompassed by the review should include:
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1)
Inspection, audit and, evaluation reports of requalification training completed by outside organizations and facility personnel.
- 2) Licensed individual performance evaluations related to l
licensed duties.
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- 3) Program oral and written examination results.
4)
Plant operational problems related to licensed individual knowledge or skills deficiencies.
- 5) Licensee Event Reports related to licensed individual performance from the plant and the nuclear irdustry.
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- 6) Changes in job assignments related to licensed duties and/or safety related functions of licensed operators.
- 7) Regulations and standards affecting licensed operator retraining.
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- 8) Assessment of licensed personnel performance deficiencies I
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Requalification program. curriculum deficiencies and licensed j
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I operator retraining needs determined by the review shall be identified, recommended corrective actions structured and a report formulated for review by the training organization through the Director of Nuclear Assurance and the operations organization through the Director, THI-1.
Requalification program deficiencies or required changes which need immediate action or significant program modification should be evaluated by the Supervisor, Licensed Operator Training as soon as practicable. Necessary corrective action shall be structured by the Supervisor, Licensed Operator Training and reviewed as above.
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h f6 4.8 RESPONSIBILITIES A.
Supervisor,. Licensed operator Training is responsible for the followingt e
Determining the scope of the Fundamer tais Paview and Operational Proficiency Lecture Series.
Determining mandatory attendance requirements at e
requalification lectures based on weaknesses on previous annual requalification avamination.
Designating those abnormal and emergency procedures to be e
q'( 3 the basis of the quis questions for each six weeks' cycle
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such that all abnorasi and emergency procedures are tested biannuallyr Preparing notification for plant management and the e
Director, TMI-1 of unsatisfactory quis results from the lecture series.
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Designating individuals to conduct overall evaluation of the annual lecture series and resolving problems described in these evaluations.
Resolving problems identified by evaluation of lecture e
v series training sessions.
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Reviewing plant drill critiques and initiating additions e
or modifications to training programs to correct performance deficiencies noted.
Ensuring performance evaluations are conducted during e
simulator and drill exercises.
Preparing notification for plant management and the e
Director, 2MI-1 of unsatisfactory skills training participation.
Specifying changes and modifications to be analysed for
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review in tbe operational review program.
Determining expanded coverage of plant design changes, e
equipment modifications, procedure changes, and technical specification changes in the Operational Pro $iciency Iacture Series.
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Specifying, in conjunction with Technical Functions, operating experience to be analyzed for training purposes and integrating the information into the training program.
besignating personnel to prepare and grade the annual e
written examination, approving the examination, answer
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C key and grading system, and reviewing the graded
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, eM examination for grading techniques and consistency.
Designating personnel to review and update the e
examination question file.
Establishing the annual oral examination schedule.
e Designating personnel to conduct oral examinations.
e Identifying significant licensed performance deficiencies e
requiring accelerated requalification programs.
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ybraulating individual accelerated requalification programs and designating individuals to conduct the associated awaminations.
Preparing reccamendations to plant management and the e
Director, TMI-l regarding the permanent removal from licensed duties or additional upgrading efforts to be considered for those individuals failing to meet the..
l standards of the accelerated requalification program.
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t Designating licensed 830's to conduct oral examinations e
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for those individuals failing to maintain an active status.
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Q Conducting an annual regualification program review and e
evaluation, submitting a report on tais review, and taking immediate corrective action where necessary.
Establishing the regualification* program records e
identified in Section 4.9.
B.
Operator Training Manager is' responsible for the following t
1 Approving the scope,of the Fundamentals Review and e
Operational Proficiency Lecture Series.
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Approving scheduling and appearance of " Guest' lecturers.
e Designating personnel to evaluate selected lecture series e
training sessions.
Reviewing repeated personnel errors or other indicators o
of degraded proficiency and initiating appropeiste training.
Approving the annual written examination, answer key and e
grading system.
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Approving accelerated requalification programs.
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Manager, Plant Training is responsible for the following:
e Approting waivers of attendance requirements for the Instructor Development Progrism.
e Designating personnel to evaluate selected lecture series training sessions.
e Ensuring that the Training Department's Administrative Support Section maintains,the records identified in P'
c Section 4.9.
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Manager of Operations is responsible for the following:
Providing inputs to the Training Department on topics to e
be presented in the Fundamentals Review and Operational Proficiency Lecture Series.
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e Approving absences of licensed personnel from lecture series.
Approving Plant Drill Scenarios, the conduct of plant e
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programs as a result of drill critiques.
e Reviewing repeated personnel errors or other indicators of degraded proficiency and initiating appropriate training.
Providing periodic observation to the Training Department e
identifying job performance results related to requalification training.
e Establishing a continuing syctes so~that licensed personnel review documented plant design changes, y
equipment modifications, procedur,e changes and technical specification changes, specifying the changes and modifications to'be analysed, and ensuring that on-shift 4
licensed personnel review the selected information in a timely manner.
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Establishing a continuing system so that licensed personnel review operating experience from TMI and applicable segments of the nuclear industry and ensuring that on-shift licensed personnel review the information
'in a timely manner.
Approving the annual written examination, answer key, and e
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grading system.
e Establishing the annual oral examination schedule.
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e Approving personnel designated to conduct oral
- o examinations.
Identifying significant licensed performance deficiencies e
requiring acce19 rated requalification programs.
Approving accelerated requalification programs.
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Approving SBO's. designated to conductoral-examinations-
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for those ind'eiduals failing to maintain an active status.
Establishing and maintaining operational review series e
participation records.
l 4.9 REQUALIFICATION PROG 1 TAM RECORDS Records of licensed individuals' performance in the requalification program shall be maintained in an auditable manner. The supervisor, Licensed Operator Trairiing is responsible for establishing the following requalification
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program records:
- 1) Oral and written examination results for each licensee.
- 2) Written examination questions and answer keys.
- 3) Ilocture series attendance records. -
- 4) Lecture series lesson plans.
- 5) Plant drill participation records.
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- 6) Reactivity manipulation and plant evolution i
participation records.
- 7) simulator training participation records.
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l These records shall be maintained by the Training f.
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Department's Ada'nistrative support.section.
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L Operational review series participation records aball be established-and maintained by tne Operations Department.
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4.10 PROGRAM APPROVAL l
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'Ibe Director of Unit 1, through the operations and
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e Maintenance Director and the Manager of Operations, certifies operators for requalification and relicensing.
The Manager of Operations retains the responsibility to c.nsure that the overall level of training of plant operators is satisfactory througo tne approval of prograa s'
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content, schedules and administrative procedures and changes thereto.
The Manager, Plant Training through the Operator Training e
Manager, is gesponsible to ensure that the training i
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program is teve1oped to meet the requirements est blished by the. Director of Unit 1 through the Manager of Operations and that proper records and documentation are provided and maintained.
1 Lesson plans fo' implementation of the training program o
shall be reviewed by the Supervisor, Licensed Operator P~
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Training and approved by the Operator Training Manager.
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All changes to this program description shall be approved o
by the Manager of Operations and Manager, Plant Training.
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APPENDIX A OFF SHIFT LICENSED OPERATOR MATCE STANDING DOCUMENTkTICat I certi2y that has satisfactorily off Shift. Licensed Operator assumed and performed the SS/SF/CRO duties (actual or under (Circle One) instruction) for the 11-7/7-3/3-11 shift on (circle one)
Date
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Shift Supervisor
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