ML19327A493

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Training Procedure TP-2-1,Revision 6, Operator Licensing
ML19327A493
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 07/29/1980
From: Susee R
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML19327A492 List:
References
TASK-1.A.2.1, TASK-TM TAC-12398, TP-2-1, NUDOCS 8008060260
Download: ML19327A493 (6)


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PORTLAND GENERAL ELECTRIC CCMPANY TROJAN NUCLEAR PLANT July 29, 1980-P4 vision 6 TRAINING PRCCE9URE TP-2-1

- OPERATOR LICENSING h

APPROVED BY g&p/

DATE I.

INTRODUCTION This training program is designed to provide the necessary education, training, and experience to prepare a candidate, normally an auxiliary operator, to successfully take a MRC reactor operator's license exami-nation. The program exercises the option of using a simulator training program in lieu of a reactor startup demonstration at the Trojan Plant.

The program consists of a ecmbination of classrcom instruction, on-the-job

. training, dedicated Control Room time, and simulator training.

An oper-ator seeking to take the license examination will normally begin this program by studying plant systems and completing systems checkouts. This self study may be supplemented by classroom lectures on plant systems.

As the operator becomes familiar with plant systems, he should begin to participate in Control Room activities for training. The majority of classroom instruction will be normally scheduled after the cperator has completed the required system checkouts and plant operations. Periodic quizzes and examinations will be given during the classroom phase of training in order to determine the student's progress. At the end of the classroom phase, the perforrance of each student will be reviewed to determine if the student will be recommended for a NRC licensing exam-ination. The evaluation will'be made by the Operations and Training Supervisors and will be based on the student's classroom performance, Control Room performance, and the results of his on-the-jcb training.

Those students who are recemmended will then participate in a simulator startup certification program followed by a prelicensing review series.

A final written and oral examination will be given to ensure each applicant is adequately prepared to take the NRC operator's licensing examination.

The time allowed to complete this program.aay vary due to the applicant's experience and the plant's operational ecmmitments. Twelve months is considered to be the normal length of tire to complete this program.

The maximum time period permitted is 18 months from the date the appli-cant assumed the position of Auxiliary Cperator. All applicants shculd TP-2-1 Page 1 of 6 Revision 6 8008060 5 0

particip-to in thiprogram lfor at least 6 months prior 'to taking tha license examination unless waived by the Training Supervisor.

II.

CURRICULUM OUTLINE-A.

On-The-Job Traininc.

1.

-In order ta ensure that the license candidate.is familiar with plant systems, he will be required to be orally examined on selected plant systems.

Either a Shift Supervisor or a member of the Training Staff will certify that the student has demon-strated. satisfactory knowledge during the oral checkout.

Training checkout forms are to be used in obtaining the required checkouts. Ccmpleted forms are to be returned to Training.

Checkouts on the following systems are required for all candi-dates:

QC-I-01 Reactor Coolant System - Overall QC-I Reactor Vessel and Internals QC-I-03

.CVCS - Letdown and Charging QC-I-04 Safety Injection QC-I-95 Residual Heat Removal QC-I-06 Centainment Spray QC-I-07 Service Water QC-I-08 Component Cooling Water QC-I-09 Auxiliary Feedwater QC-I-10 Emergency Diesels QC-I-11.

Fuel Handling QC-II-01 Safeguards and Containment Isolation E

QC-II-02 Reactor Protection QC-II-03 Pressuriser Pressure and Level QC-II-04 Steam Generator Level and Feed Pump Speed QC-II-05 Steam Dump QC-II-08 Excore Instrumentation QC-II-09 Incore Instrumentation QC-II-10 Full Length Rods QC-II-12 Digital Rod Position Indication QC-II-13 Rod Insertion

' QC-III-01 230 KV System QC-III-02 480 Volt System QC-III-03 120 VAC Preferred and Non-Preferred QC-III-05 125 VDC System QC-III-09 12 KV-System QC-III-10 4 KV System QC-IV-08' Spent Fuel Pool Cooling and Purification QC-IV-10 Spent and New Fuel Pits QC-V-01 Main Steam QC-V-04 Main Turbine and Supervisory TP-2-1 Page 2 of 6 Revisic. 6 4

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QC-V-05

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'QC-V-12' Feedwater and Condensate QC-V-13 Main Feedwater Pump and Turbine

'QC-V-18~

Steam Generator slowdown QC-VI-01.

Containment H&V QC-VI-04 Control Room H&V QC-VII-01 Clean Radioactive Waste QC-VII-02 Dirty Radioactiva Wastt QC-VII-03 Solid Radwaste QC-VII-04 Gaseous Radioactive. Waste QC-VII-08 Vent Collection QC-IX-01 Containment Building Design QC-IX-02 Service and Instrument Air QC-IX-04 Fire Protection QC-IX-20 Diesel Fuel Oil QC-X-05 Portable H.P.

Instruments QC-X-06 Radiation Monitoring Attendance at classroom lectures and passing a written exmn on the subject may be accepted in lieu of receiving a formal check-out.

This option may be exercised with the aoproval of the Training Supervisor.

Bimonthly the Training Supervisor will forward to the Cperations Supervisor a report on the checkout progress of each of the candidates.

2.

All license candidates will receive practical training in the manipulation of power plant controls and general Control Room operations. Each applicant must manipulate the controls of the Trojan Nuclear Plant during at least five significant reactivity

. changes.

Evolutions which are acceptable to fulfill this require-ment are:

e a.

Reactor startup.

b.

Reactor shutdown.

c.

Manual control of steam generator.

d.

Manual control of the turbine generator during a load change of greater than 10%.

l e.

. Boration during power operation.

f.

Dilution during power operation.

g.

Operation of manipulator crane during refueling.

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Any significan't changas in manuni rod control' L > 10% powar).

1.

. Manual rod control during generator synchronization.

In -addition to reactivity manipulations the applicant shall par-ticipate in other Control Room activities. Three months of the applicant's training period shall be devoted to Control. Room Operation. During this period, he shall perform all duties normally performed by licensed-operators, under the direct supervision of a Reactor Operator. fThis dedicated Control Room period shall be supervised by the Shift Supervisor with guid-ance provided by the Training Department. Whenever a non-licensed individual actively parti-ipates in any plant evolutions in the Control Room, he'should document his participation on i

Training Form RM.

He should include the date, time spent, and a description of the activity performed. The Control Operator initials the form at the end of each' shift. Some examples of the types of activities that should be documented are a.

~ Component Cooling Water or Service Water train rotation.

b.

Starting and loading of emergency diesel.

. c.

_ Containment. purge.

d.

Placing a feedwater pump in service.

e.

Rotation of charging pumps.

f.

- Transferring auxiliary electrical buses.

Each individual is responsible for maintaining his own records of Control Room activities by the use of Control Room Partic-ipation Forms. At the end of the month, each license candidate will forward the ccepleted forms for that month to the-Training i

Supervisor.

B.

CIASSROCM INSTRUCTION 1

A lecture series presented by qualified instructors frem the plant staff ~ or contractor personnel will be given.

Instructors who teach 2

systems, integrated responses, transient and simulator courses shall hold a Senior Reactor Operator license or shall have successfully completed a Senior Operator examination.

The. amount of classroom instruction received by each applicant will be ~ determined by his previous nuclear experience.

In general, appli-cants with no previous nuclear experience will participate in 2> 475 hours0.0055 days <br />0.132 hours <br />7.853836e-4 weeks <br />1.807375e-4 months <br /> of formal classroom instruction. The lecture series will cover the following topics:

1.

Fuel Handling.

1 1

2.

Radiation Protection.

- 3.

Plant Mechanical and Electrical Systems.

TP-2-1 Page 4 of 6 Revision 6' 5

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'4.

' Instrumentation and Control.

5. -

Security.

6.

Radiological Emergency Response Plan.

7.

Technical Specifications.

8.

Administrative Orders / Operating Instructions.

9.

Ewrgency Instructions /Off Normal' Instructions.

10.

Radicactive Waste System.

11.

_ Trojan Plant Systers.

12.

Plant Characteristics and Control.

13.

Nuclear and Reactor Physics.

14.

Plant Transients and Accident Analysis.

15.

Chemistry.

16.

Reactor Safeguards.

17.

Heat Transfer, Thermodynamics, and Fluid Flows.

18.

Mitigation of Accidents involving a degraded core.

Those applicants with previous nuclear experience at either commer-cial or naval nuclear power plants sdll be required to participate in a minimum of 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> of classrocm lectures. The topics covered will be the same as those listed above; however, the amount of time spent covering plant systems will be greatly reduced.

Knowledge of plant systems will be gained by self study. A written examination on plant systems will be given to each applicant during the classrocm phase of training.

As a final preparation prior to taking the license examination, all license candidates will participate in a prelicense review series.

j The two-week course will consist of a combination of classrecm instruction, subject review, written quizzes, oral examinations, and homework assignments.

C.

Simulator Training Each candidate will satisfactorily complete a NRC-approved training program of' at 'least ene week duration at' a nuclear power plant simulator.

D.

Evaluation The performance of license candidates during the classrocm phase will be routinely evaluated through periedic. qui==es and examinations.

TP-2-1 Page 5 of 6 Revision 6

At the completien of the program, a writt n and oral exam, similar to the NRC exams in content and time allotment, shall be given. Quisses and examinations will be prepared and admin-istered by the Training Staff.and graded by a member of the Training Staff. The Training Supervisor will approve all qui =:es and examinations and will review them for grading techniques and consistency.

A grade of 70 percent or greater on the quizzes and 80 percent overall or 70 percent on a section for the simulated NRC exam is considered to be satisfactory.

Any license candidate failing to meet this criterion will be assigned remedial study by the Training Supervisor and will be reexamined in the deficient area.

The reexamination may' consist of either another written quis or examination, or an oral examination administered by an individual designated by the Training Supervisor.

The oral examinations will be conducted by Senior Reactor Operator personnel as scheduled and assigned by the Training Supervisor.

E.

Senior" Cperator License Each Senier Operator candidate shall possess or have possessed, a operators lacense for at least one year prior to taking a NRC admin-istered Senior Reactor Operator License examination.

If the operator license is for a facility other than Trojan the applicant shall par-ticipate in Sections A through D of this procedure.

Additionally, he shall have a minimum of 4 years responsible power plant experience, or

' years power plant experience and 2 years of academic or technical training related to nuclear power. Two years must be nuclear power plant experience of which at least 6 months shall be at Trojan. After satisfying all criteria in A through D of this procedure, the ap-plicant must have 3 months of shift training as an extra man on shift.

Preferably this 3 months snould be concurrent with the en-the-job training performed during the operator licensing phase of this pro-cedure.

F.

Ad ainistration The following records will be maintained by the Training Supervisor:

1.

copies of examinations and quizzes.

2.

Examination and qui: grades.

3.

Records of on-the-job training.

4.

Records of simulator training.

5.

Oral examination results.

4 TP-2-1 Page 6 of 6 Revision 6

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