ML19327A531

Training Instruction TI-202 Replacement Training for Senior Licensed Operating Personnel, Revision 1

ML19327A531
Person / Time
Site:	Brunswick
Issue date:	07/25/1980
From:	Jonathan Brown, Michael Jones, Tollison A CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19327A523	List: ML19327A522 ML19327A526 ML19327A529 ML19327A531
References
TI-202, NUDOCS 8008060334
Download: ML19327A531 (7)

Text

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT TRAINING INSTRUCTION TI-202 Replacement Training for Senior - Licensed Operating Personnel -

Revision 1 NM Recomended By: / Date: 7 / ?J /fo

'"daining Supervisor Recomended By:

Date: 7M 7 #

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• d Ope ns Mana r Approved By: Date: 7-7 General Managbr l

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8 0080 803 3Y '

LIST OF EFFECTIVE PAGES TI-202 Page Revision 1 1 2 0 3 0 4 1 5 1 BSEP/TI-202 Rev. 1 f l

TRAINING INSTRUCTION NO. 202 REPLACEtlCNT TRAINING FOR SENIOR-LICENSED OPERATING PERSONNEL 1.0 Purpose To ensure Senior Operator replacement personnel receive suffient training to meet or exceed the requirements of ANSI Standard N18.1-1971 and 10 CFR 55.

It is intended that graduates of this program will be prepared to pass the NRC hot license examination for Senior Reactor Operator and to supervise the safe and efficient operation of the Brunswick Plant.

2.0 Procedure Prior to participating in an NRC Senior Reactor license examination each candidate will:

a. Hold a high school diploma or its equivalent,

b. Have at least four years of power plant experience, at least two years of which is nuclear power plant experience, of which at least six sonths shall be on the Brunswick Plant,

c. Hold a valid NRC Reactor Operator license or will have satisfactorily completed the appropriate training specified in Training Group In-struction 201, " Brunswick Plant Operator Replacement Training,"

d. Satisfactorily complete the additional training for Senior Operator candidates described in the paragraphs following, and

e. Have held an operator's license for at least one year.

The Senior Operator Replacement Training Program will consist of classroom training and on-the-job training. Candidates will receive at least three months' experience (0JT) as an extra man in the Control Room. Classroom training will include at least:

a. Reactor Theory - Instruction in this category will encompass more ,

detail than required for Reactor Operator License candidates. Train- 1 ing will include the specific quantitative values for the Brunswick Plant and will emphasima the understanding and utilization of mathe-matical expressions governing reactor behavior in the following areas:

1. The fission process

2. Neutron multiplication

3. Source and control rod effects

4. Reactivity coefficients ,

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BSEP/TI-202 1 Rev. 1 l l l

2.0 Procedure (cont'd)

5. The critical condition

6. Heat transfer

7. Fluid flow characteristics

b. Radioactive Material Handling, Disposal and Hazards

1. 10 CFR 20 -

2. Special Nuclear Material Accountability

3. Radiation Protection Manual

4. Radiation Work Permits S. Radioactive discharges - procedures, limitations, precautions

6. Calculations (a) Time, distance, shielding (b) Radioactive decay (c) Dose and dose rate conversions

7. Radiation processing and monitoring equipment

c. Specific Operating Characteristics - This category of instruction will constitute a review of subjects required for the " Operating Characteristics" portion of the Reactor Operator Replacement Training Program, TI-201. It will proceed beyond the scopa of knowledge required for routine plant operation and will include the use of curves and graphs to explain the causes, limitations and effects of changes in the reactor core and Nuclear Steam Supply and auxiliary systems. Instruction will include, but will not be limited to:

1. Reactor Control (a) Integral and differential rod worths.

(b) Period vs. reactivity (c) Reactivity and power coefficient curves (d) Ienon and Samarium curves

2. Core flow map BSEP/TI-202 2 Rev. O

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9 2.0 Procedure (cont'd)

3. Electro-hydraulic control system

4. Boiling and heat transfer in the core

5. Integrated plant response to design basis accidents and abnormal operational transients, including safety system functions which occur to limit, contain and terminate the transients. -

d. Fuel Handling and Core Parameters

1. Fuel characteristics (a) Mechanical (b) Uyclear (c) Thermal (d) Decay heat

2. Fuel leak detection

3. Fuel storage facilities

4. Fuel handling (a) Core alterations (b) Tools and equipment (c) Fuel handling and inspection procedures

5. Inadvertant criticality (a) Incidents (b) Recognition (c) Refueling interlocks and other prevention measures

6. Inverse count rate calculations

e. Administrative Procedures, conditions and limitacions

1. Technical Specifications

2. Facility Operating License l

BSEP/TI-202' 3 Rev. 0 -l

2.0 Procedure (cont'd)

3. P.O.M, Volume I, Administrative Procedures

4. Corporate QA Manual. Part 2 .

5. P.O.M., Volume XIII, Emergency Plan

6. FP-7

7. 10CFR50, 55 and 115

8. P.O.M., Volume IV, General Operating Procedure

f. Heat Transfer, Fluid Flow, and Thermodynamics

1. Basic properties of fluids and matter

2. Fluid statics

3. Fluid dynamics ,

4. Heat transfer by conduction, convection, and radiation

5. Change of phase boiling

6. Burnout and flow instability

7. Reactor heat transfer limits ,

g. Mitigating Core Damage

l. Incore instrumentation ,

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2. Excore nuclear instrumentation ,

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3. Vital instrumentation 4 Primary chemistry

5. Radiation monitoring

6. Gas generation

h. Transient and Accident Analysis i

1. Anticipated transients l

2. D'e sign basis accidents BSEP/TI-202 4 Rev. 1 l

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2.0 Procedure (cont'd)

The entire content of the listed documents might not be presented in formal lectures, but quizzes and examinations will require detailed knowledge to the extent required of a Senior Control Operator or Shift Foreman in the performance of his duties.

Throughout the Senior Operator Replacement Training Program, candidates progress will be evaluated through a combination of quizzes, examinations and/or oral examinations. -

Instructors who teach systems, integrated responses, transient and simulator courses shall hold a valid SRO license or pass an NRC SRO examination and  !

participate in the retraining program.

3.0 Responsibility 3.1 Operations Manager The selection of candidates, the method (s) used for the selection of candidates and the determination of the duration and content of training for each candidate will be the joint responsibility of the General Manager, the Operations Manager and the Training Supervisor.

3.2 Training Supervisor 3.2.1 The Training Supervisor will be responsible to the Director of Nuclear Safety and Quality Assurance for: l (a) The axacution and overall conduct of the Senior Operator Rep.3 cement Training Program.

(b) Timely initiation of requests to the NRC for license examinations.

(c) The proper maintenance of records pertaining to this training program.

4.0 Documentation .

Senior Operator Replacement Training and candidate performance will be documented by the Training Supervisor on Attachments (1) and (2) to Training Instruction 201. All documentation for a replacement training program will be retained by the Training Supervisor for use in compiling and substantiating data used for NRC hot license exam requests.

BSEP/TI-202 5 Rev. 1

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