ML19327A529
| ML19327A529 | |
| 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: |
| References | |
| TI-201, NUDOCS 8008060331 | |
| Download: ML19327A529 (10) | |
Text
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CAROLINA POWER & LIGHT COMPA W BRUNSWICK STEAM ELECTRIC PLLTI TRAINING INSTRUCTION TI-201 Brunswick Plant Reactor Operator Replacement Training Program Revision 3 l
Recotr. ended By:
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T ning Supervisor Reco::nnended By:
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Q LIST OF EFFECTIVE PAGES TI-201
- lage, Revision 1
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BSEP/TI-201 Rev. 3
TRAINING INSTRUCTION NO. 201 i
BRUNSWICK PLANT REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM 1.0 Purpose The purpose of the Brunswick Operator Replacement Training Program is to ensure that operator replacement personnel are provided with suffi-cient formal and on-the-job training to meet or exceed the requirements of ANSI Standard N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel," and 10CFR55, " Operator's Licenses." It is intended that graduates of this program be prepared to pass the NRC hot license examinations and operate the Brunswick Plant in a safe and efficient manner.
2.0 Procedure No single training program can account for the wide differences in training and experience that may be encountered 'in candidates selectad for operator replacement training. Three general categories of replace-ment candidates are recognized. They are those having:
a.
Previous BWR power plant operating experience, b.
Previous PWR power plant (including Navy nuclear power) operating experience, and c.
Little or no previous nuclear experience.
The training program described in this instruction represents the minimum training for candidates having little or no previous nuclear experience.
The Training Supervisor may exempt candidates from portions of training by documenting previous experience or expertise.
He may adjust scope and content of various phases of training to fit individual needs through consultation with the Manager - Operations, using the applicable NRC regulatory guides.
Prior to participating in an NRC license examination, each candidate will hold a high school diploma and will have at least two years of power plant experience, at least one year of which is nuclear power plant experience.
The Operator Replacement Training Program is divided into four phases:
1.
On-The-Job (RTGB) Training 2.
Classroom Training i
3.
Reactor and Simulator Experience
{
l 4.
Review i
l BSEP/TI-201 1
Rev. 3
2.0 Procedura lCont'd)
Training need not be accomplished in the above specified order. Following is a description of each phase of training:
2.1 Phase I: On-The-Job (RTGB) Training During this phase, candidates will participate in a three-month program of on-the-job training which involves:
a.
Manipulation of the nuclear plant controls under instruction during day-to-day operations.
b.
Experience in training startups and shutdowns of the reactor (if possible), and c.
Instruction and counseling from licensed operating personnel to facilitate the candidates' understanding of overall plant performance, system design and performance and operating j
procedure.
j l
During Phase I the candidate will complete the following:
l.
Reactor Turbine Gage Board (RTG3) on the Job Training Final Check List, and 2.
Reactor Tar
- Board (RTGB) on the Job Training System and Practf
.-.or Check Lists.
i The Shift Foreman to whom the candidates are assigned will oversee their training activities and will report their training to the Training Supervisor. When it has been determined that a candidate has received sufficient training and experience as documented on the Reactor Turbine Gage Board (RTGB) on the Job Training Final Check List, he will be permitted to continue with further phases of the NRC reactor operator hot license training program for the Brunswick Plant.
I 2.2 Phase II: Classroom Training This phase will consist of 10 to 12 weeks of classroom training.
Candidates will be removed from shift rotation and placed in a full-time training status, and witl report administratively to the Training Supervisor or his designated assistant.
Instruction during this phase will include, but will not be limited to, the following topics:
i a.
Reactor Theory and Principles of Reactor Operation 1.
Atomic and nuclear physics
.BSEP/TI-201 2
Rev. 3
2.0 Procedure (Cont'd) 2.
Fission procass 3.
Neutron multiplication 4.
Reactivity 5.
Reactivity coefficients 6.
Reactor control 7.
Rod worth 8.
Xenon, samarium and control poison effects 9.
Design Features 1.
Nuclear Steam Supply Systam a.
Reactor vessel and internals b.
Fuel c.
Recirculation system d.
Reactor Vater cleanup 2.
Steam, condensate, feedwater and related systems 3.
Turbine generator and supporting systems 4.
Safety systems a.
HPCI b.
ADS c.
Core spray d.
RHR/LFCI e.
Diesel generator emergency power f.
Standby liquid control BSEP/TI-201 3
Rev. 2 4
2.0 Procedure (Cont'd) 5.
Electrical distribution a.
230 KV, 24 KV b.
4160 V c.
125 VDC, 24 VDC c.
Operating Characteristics 1.
Reactor control a.
Control rod manipulations b.
Recirculation flow control c.
Electro-hydraulic control system d.
Xenon transients 2.
Core flow map 3.
MCPR, MLHCR, MAPLEGR 4.
Safety analyses a.
Abnormal operational transients b.
Design basis accidents d.
Instrumentation and Control Systems l.
Nuclear instrumentation 2.
Reactor manual control 3.
Rod position indication 4.
Rod sequence control system 6.
Recirculation pump speed control 7.
Electro-hydraulic control system BSEP/TI-201 4
Rev. 2
2.0 Procedure (Cont'd) 8.
Reactor vessel level control U
9.
- 10. Primary containment isolation 11.
Steam leak detection
- 12. ECCS initiation and control logic e.
Standard and Emergency Operating Procedures 1.
Precautions and limitations 2.
Overall plant operating procedures (GP-1) 3.
Emergency instruction i= mediate actions 4.
Energency plan and procedure f.
Radiation Control and Protection 1.
Radiation and cohtamination 2.
Biological effects 3.
Time / distance, shielding 4.
Monitoring systems and instruments 6.
Radiation procedures 3
Chemistry 1.
Chemistry control and limits 2.
Chloride intrusion h.
Technical Specifications 1.
Organization and format 2.
Safety limits and limiting safety system settings 3.
Discharge limits BSEP/TI-201 5
Rev. 2
I 2.0 Procedure (Cont'd) i 1.
Quality Assurance Responsibilities for Operations Personnel j.
Heat Transfer, Fluid Flow, Thermodynamics i
1.
Basic properties of fluid and matter 2.
Fluid statics 3.
Fluid dynamics 4.
Heat transfer for conduction, convection, radiation 5.
Changa of phasu - boiling 6.
Burnout and flow instability 7.
Reactor heat transfer limits k.
Mitigating Core Damage 1.
Incore instrumentation 2.
Excore nuclear instrumentation 3.
Vital instrumentation 4.
Primary chemistry 5.
Radiation monitoring 6.
Cas generation Instructors who teach systems, integrated response, transient and simulator courses shall either hold a valid SRO license or l
pass the NRC SRO axamination and participate in SRO retraining.
2.3 Phase III: Reactor and Simulator Experience This phase of training will have two parts:
University Reactor Startup Experience (optional) a.
b.
BWR Simulator Hot License Certification The university training vill provide students with observations of f.
nuclear instrumentation responses during suberitical multiplication, approach to criticality and supercritical operation.
This training 1
I BSEP/TI-201 6
Rev. 3
4 2.0 Procedure (Cont'd) l will last approximately two weeks, and will normally be scheduled during Phase II.
The one week of BWR Simulator Hot License Certification training will normally be used in lieu of the reactor j
startup operating test at the Brunswick Plant, as required by 10CFR55.
2.4 Phase IV: Review During this phase, a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> will be used for review, audit eraminations, and evaluation of the candidate.
This training I
will normally consist of both on-shif t and classroom training.
Throughout the Operator Replacement Training Program, the candidates' progress will be evaluated through a combination of qui::es, written examinations, and/or oral examinations.
3.0 Responsibility 3.1 Operations Manager The selection of candidates, the method (s) used for the selection of canaidates and the determination of the duration and content of train-ing for each candidate will be the responsibility of the Operations Manager.
3.2 Training Supervisor 3.2.1 The Training Supervisor will be responsible to the Director of Nuclear Safety and Quality Assurance (DNS) for:
a.
The execution and overall conduct of the Operator Replacement Training Program.
b.
Timely initiation of requests to the NRC for hot license examinations.
3.2.2 The Training Supervisor or designated assistant will be responsible to the Director of Nuclear Safety and Quality Assurance for the proper maintenance of records pertaining to this training program, including:
a.
Copies of lesson ple.ns and instructional aids, b.
Copies of examinations administered and the answers provided by the candidates, l
l c.
Lecture attendance and grade sheets, and d.
Training reports.
BSEP/TI-201 7
Rev. 3
3.0 Responsibility (Cont'd) 3.3 Shift Foremen Shift. Foremen will be responsible for the supervision and recording of training during Phase I for candidates assigned to their shifts.
4.0 Documentation Documentation of training obtained under this procedure will be kept on file in accordance with plant filing instructions.
It will be used to substantiate information on license applications and certifications, i
i 1
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BSEP/TI-201 8
Rev. 3 4
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