ML20093E734

Rev 6 to Training Instruction TI-201, Brunswick Plant Reactor Operator Replacement Training Program

ML20093E734
Person / Time
Site:	Brunswick
Issue date:	10/05/1984
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20093E668	List: ML20093E666 ML20093E734
References
TI-201, NUDOCS 8410120232
Download: ML20093E734 (11)

Text

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, 9 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT l

BRUNSWICK PLANT REACTOR OPERATOR REPLACEMENT TRAINING PROGRAM F

i: TRAINING INSTRUCTION: TI-201 l

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VOLUME I Rev. 006 l

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\ y Approved ByT8// At c 0, - - --

, ' '/ /' General Manager /

Director - Training 4

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r 8410120232 841005 PDR ADOCK 05000324 V PDR E '. .i __ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _

u LIST OF EFFECTIVE PAGES TI-201 Page(s) Revision 1-9 6 l

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1.0 Purpose The purpose of the Brunswick Operator Replacement Training Program is to ensure that operator replacement personnel are provided with sufficient formal and on-the-job draining to meet or exceed the requirements of ANSI Standards N18.1-1971 and ANSI /ANS-3.1, 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 2.1 No single training program can account for the wide differences in prior training or experience that may be encountered by the prospective candidates of this program. To equalize the candidate's entry level, each candidate will satisfactorily complete the Auxiliary Operator qualifications prior to enrolling in this program.

2.2 The training program described in this instruction represents the minimum training for candidates having little or no previous nuclear experience. The Director - Training retains the option of giving entrance examinations to class candidates to determine their entry level and ability to complete the program. He may adjust the scope and content of various phases of the program to fit 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 expetience, at i least one year of which is nuclear power plant experience. The Operator Replacement Training Program is divided into four basic phases:

2.2.1 Classroom training 2.2.2 Simulator 2.2.3 Plant on-the-job' training 2.2.4 Simulator certification Training is recommended in the a~oove order but may be altered to fit special circumstances. The following is a description of each phase of training:

2.3 Phase 1: Classroom Training This phase will consist of two classroom periods. The first period will last approximately six weeks and will include, but will not be limited to, the following topics:

2.3.1 Reactor

Theory and Principles of Reactor Operation BSEP/Vol. I/TI-201 1 Rev. 6

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.j 4 l 2.3.1.1 Atomic and nuclear physics h ' 2 . 3 .1 ~. 2 Fission process

-2.3.1.3 Neutron multiplication n

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2.3.1.4 Reactivity.

2. 3 .1 ~. 5 Reactivity coefficients 2.3.1.6 Reactor control i

2.3.1.7 Rod worth 2.3.1.8 Xenon, samarium, and control poison effects 2.3.1.9 Shutdown margin 2 3.2 Quality Assurance Responsibilities for Operations Personnel 2.3.3 Heat Transfer, Fluid Flow, Thermodynamics 2.3.3.1 Basic properties of fluid and matter 2.3.3.2 Fluid statics 2.3. 3.3 ~ Fluid dynamics 2.3.3 4* Heat transfer for conduction, convection, radiation i 2.3.3.S' Change of phase--boiling i

'2.3.3.6 Burnout 1and flow instability 1 2.3.3.7 Reabtor heat tr'ansfer limits t

2.3.4- Radiation Control and Protection t,

.!, 2.3.4.1- Radiation and contamination l

.2.3.4.2 Biological effects

. 2.3.4.3 Time / distance, shiel' ding 2.3.4.4 -10CFR19, 10CFR20, 10CFR100 2.3.4.5- Monitoring systems and instruments 2.3.4.6 Radiation procedures I

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"U 2.3.5 . Chemistry 2.3.5.'1 Chemistry control and limits 2.3.5.2 . Chloride intrusion 2.3.6 -Technical Specifications 2.3.6.1 Organization and format 2'3.6.2

. Safety limits and limiting safety system settings 2.3.6.3 Discharge limits The'second classroom phase will last approximately 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> ~and will normally consist of five 4-hour sessions per week for.approxi-mately.15 weeks. -(The remaining four hours per day will consist of simulator training, described later.) This phase of training will consist of, but not l>e limited to, the following topics:

2.3.7 - Design Features 2.3.7.1 Nuclear Steam Supply System E

2.3.7.1.1 Reactor vessel and internals 2.3.7.1.2 Fuel 2.3.7.1.3 Recirculation System 2.3.7.1.4 Reactor water cleanup 2.3.7.2 Steam, condensate, feedwater, and related systems 2.3.7.3 Turbine Generator and Supporting Systems 2.3.7.4 Safety systems 2.3.7.4.1 HPCI 2.3.7.4.2 ADS 2.3.7.4.3 Core Spray 2.3.7.4.4 RHR/LPCI 2.3.7.4.5 Diese1' Generator Emergency Power i

2.3.7.4.6 Standby Liquid Control BSEP/Vol. I/TI-201 3 Rev. 6 C

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2.3.8 :Mit'igatingyoreDamage 2.3.8.1 In-core instrumentation

, 2.3.8.2  : Vital instrumentation .

2.3.8.3 Coolant chemistry 2.3.8.4 Radiation monitoring 2.3.8.5 Gas generation

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~ 2.3.9 Electrical Distribution 2.3.9.1 230 kV, 24 kV

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2.3.9.2 4160V 2.3.9.3 125 Vde, 24 Vdc

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1 2.3.'10 Operating Characteristics 2.3.10.1 Reactor control 2.3.10.1.1 Control rod' manipulations 2.3.10.1.2 -Recirculation flow control

. 2.3.10.1.3 Electro-Hydraulic Control System 2.3.10.1.4 Xenon transients ,

i 2.3.10.2 Core flow map l, 2.3.10.3 MCPR, MLHGR,liAPLHGR

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2.3.10.4 Safety analysis 2.3.10.4.1 Abnormal operational transients

'2.3.10.4.2 Design basis ac'cidents -'

2.3.11 Instrumentation and Control Systems 2.3.11.1 Nuclear Instrumentation 2.3.11.2 Reactor Manual Control 2.3.11.3' ' Rod Position Indication

', ~2.3.11.4 Rod Worth Minimizer l

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'2.3.11.5 Rod Sequence Control System 2.3.11.6 Recirculation Pump Speed Control 2.3.11.7 Electro-Hydrau ic Control System 2.3.11.8 Reactor Vessel Level Control 2.3.11.9- Reactor Protection System 2.3.11.10 Primary Containment Isolation i

2.3.11.11 Steam Leak Detection 2.3.11.12 ECCS. Initiation and Control Logic 2.3.12 Standard and Emergency Operating Procedures 2.3.12.1 Administrative procedure 2.3.12.1.1 Duties and responsibilities 2.3.12.1.2 Conduct of Operations 2.3.12.1.3_ Overall plant operating procedures-2.3.12.2 Precautions and ifmitations 2.3.12,3 Cverall plant operating procedures (GP

• GP-10) 2.3.12.4 Emergency Operating Pro'edures c (flow path.)

l 2.3.12.5 Abnormal Operating Procedures 2.3.12.6 Emergency Response Plan'and Plant Emergency Procedures  ;

2.4 Phase 2: erience Simulator and Reactor Startup Exp!

-This phase of training may consist of two parts:,

Part 1 - Simulater training, including simu'lator.

certification The simulator training phase will last approximately 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> and will normally consist of five 4-hour sessions per week for approxi-mately 15-weeks. The general concept of the simulator training will l-be to enhance the ability of candidates to competently operate the Brunswick plant during normal operation and analyzed transient

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Instruction during.this period shall include:

2.4.1 Standard and emergency _ operating procedures

, i 2.4.21f Plant transients n

-2.4.3 Accident identification and analysis, including trending 2.4.4 Controlling the plant from a central Control Room during normal;, abnormal, and emergency situations 2.4.5 Operatyngphilosophy,useofprocedures,shiftandrelief turnover, and verification of system status As a minimum, the license candidate shall participate in training sessions that include the following manipulations:

2.4.6 Plant or reactor startups, to include a range that reactivity feedback from the nuclear heat addition is noticeable and heatup rate is established 2.4.7 Plant shutdown J

2.4.8 Hanual control of feedwater during startup and shutdown 2.4.9 Standb'y liquid control use during power operation 2.4.10 Any significant (10 percent) power changes due to manual changes in control rod position or recirculation flow 2.4.11 Any re'a ctor power change of 10 percent or greater where load change is performed with load limit control or where flux, temperature, or speed control is on manual 3 2.4.12 Ioss of coolant' including:

2.4.12.1 .Inside and outside primary c atainment i

2.4.12.2 Large and small, includina, ak rate determination 2.4.13 Loss of instrument air if simulated plant specific l I

2.4.14 Loss of electrical power or degraded power sources (or j both): i I

2.4.15 Loss cf core coolant flow / natural circulation  !

I 2.4.16 Loss of condenser vacuum 2.4.17 Loss of service water l

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'2.4.18L Loss of shutdown cooling g.2. 4 .19 Loss.of Component Cooling-System-or. cooling to an

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a- 2.4.20- Loss of normal feedwater or normal Feedwater System

. . -*' failure

-2.4.21. Loss-of all feedwater (normal and emergency)

'2.4.22 Loss of Protective System channel 1 -

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i- 2.4.23 'Mispositioned control rod or rods 2.4.24 Inability to drive control rods 2.4.25 Fuel cladding failure or high activity in reactor coolant ^

i. -or off-gas

.2.4.26 Turbine or generator trip 2.4.27- Malfunction of automatic control system (s) which affect

~l' . reactivity g:, ,

2.4.28 , Malfunction of reactor coolant pressure / volume control system 2.4.29 . Reactor trip

-2.4.30 Main speam linei break (inside or outside containment) l- 2.4.31 Nuclear instrumentation failure (s)

,: Participants will be in groups of no more than four people

' manipulating the controls or directing the activit'ies of individuals

'! .during plant exercises.

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j Part"2 - University Reactor Startup Experience (Optional)

'The university training-will provide the candidates with obserystions of nuclear instrumentation responses during subcritical multiplication,

~~g j ' approach to criticality,'and subcritical operation. Also included

, in this program ars. experiments'cencerning radiological and chemistry topics. This training.will last approximately five days

}li ' and will normally be scheduled after completion of Phase 1 classroom F . training.

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y 2.5 Phase 3: RTGB On-the-Job Training After the candidates successfully~ complete 13 weeks of simulator training they .will be assigned to the Operations group for a-minifum.o,f12=weeksRTGB'on-the-jobtraining. During this period, the' candidate will operate the Brunswick plant under the instruction of a-licensed Control Operator... Evolutions will be documented by

.the candidate and reviewed daily by the Shift Foreman.

2.6 Phase-4

Simulator Certification A simulator 'f fnal certification will be provided, to include the minimum requirements.as listed in ANSI-3.1-1981 (5.2.1.3.2), such that the candidate must competently demonstrate the ability to:

2.6.1 Manipulate controls in a safe and competent manner 2.6.2 Predict instrument response and use the instrumentation available 2.6.3 . Follow facility procedures 2.6.4 .Undhrstandalarmsandannunciatorsandtakeproperaction 2.6.5 Com unicate promptly and effectively

3.0 Responsibility 3.1. Manager 2 0perations

-1Rie selectionj of candidates will'be the' responsibility of the Manager - Operations and the Director - Training. No more than 12 candidateswi%1beselecte'dtoenterthesimulatorphaseofthis training program. ]

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4 3.2 Director - Training

3. 2.1 ~ The; Director-Trainingwillberesponsibletothe Manager - Nuclear Training Section.

The' Director - Training will be responsible-for the fol;1owing (concerning operator-training):

3.2.1.1' The execution and overall conduct of the Operator Replacement Training Program 3.2.1.2 Timely initiation of license applications for the NRC hot' license examinations 3.$.1.3 Determination of the duration and content of Hot License Training Program BSEP/Vol. I/TI-201 8 ,

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!The-Director l zTraining or designated assistant'w'il'l be-

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. responsible-to the Manager - Nuclear Training Sedtion for

the -proper maintenance of records pertaining to this

training program, including:

3.2.2.1 1 Copies of' study material,11esson plans, and.

instructional aids R3.2.2.2~ , Copies of examinations administered and the y answers provided by the candidates 3.2.2.3 Lecture attendance and grade sheets -

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Jt - 3.2.2.4 Training reports as required

? 3. 3 ' Shift Foremen i / Shift Foremen will be responsible for the supervision of training during Phase 3-for. candidates assigned to their shifts.

l4.0' -Documentation

-b _ Document'ation-of training obtained under'this procedure _will be kept-Lon

(file in~accordance with

plant. filing instructions. :It will be used to

substantiate .information cnt _ license applications andicertifications.

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