ML20100G504

Forwards Changes to Rev 1 to FSAR Chapter 13 Re Operator Training & Qualification,In Response to 850320 Request & 840401 Telcon.Changes Will Appear in Amend 16 to FSAR

ML20100G504
Person / Time
Site:	Vogtle
Issue date:	04/02/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-572, NUDOCS 8504080271
Download: ML20100G504 (30)

Text

Georgia Power Company Rout) 2, Box 299A W*ynesboro Georgia 30830 Telephone 404 554 9961 404 724 8114 f

Southern Company Services, Inc.

Post Office Box 2625 l

Birmingham. Alabama 35202 Te!ephone 205 870E11 Vogtle Proj.ect April 2, 1985 Director of Nuclear Reactor Regulation Fle: X3BC35 Attention:

Ms. Elinor G. Adensam, Chief Log: GN-572 Licensing Branch #4 Division of Licensing U. S. Nuclear Regulation Commission Washington, D.C.

20555 REF: GN-547, DATED 3/20/85, BAILEY TO DENTON NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 REQUEST FOR SUPPLEMENTAL INFORMATION DRAFT REVIEW COPY OF FSAR CHAPTER 13, REV. 1

Dear Mr. Denton:

As a result of a teleconference with members of your staff on April 1, 1985, changes to the subject document., transmitted to you by the referenced letter, have been made as indicated in the attachment. These changes will appear in Amendment 16 to the FSAR.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely, e

J. A. Bailey Project Licensing Manager JAB /sm Enclosure xc:

D. O. Foster R. A. Thomas G. F. Trowbridge, Esquire J. E. Joiner, Esquire C. A. Stangler L. Fowler pk M. A. Miller L. T. Gucwa g

G. Bockhold, Jr.

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THE MINIMUM NUMBER OF PERSONNEL BOTH UNITS OPERATING

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PERSONNEL TOTAL PER DEPARTMENT 72

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_P,LANT ORGANIZATION Georgia Pbwer ELECTRIC GENERATING PLANT

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FIGURE 13.1.2-l_{ SHEET 1 OF 3) 3605-0 s

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emTAL TEST 37 111 SEE LINE B 'SMEET ONE SUPERmTENDENT SUPERusTENDENT SUPER.TENDENT SUPT OF SUPT OF 0FENGR5vCS OF ENGR uA50m 0F PLANT ADWHs MP CHEM MAMTEhANCE 13 gfg 13 1/1 25 25/25 35 1/1 93 1/1 I

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$UPERvlSOR 2/2 2/2 1/1 1/1 1/1 2/3 1/2 1/1 Chtestav tas MEALTN MATERIAL MamTENANCE I&C ENGmEERS ENGmEERS 8,',g suPEnv404 PMySIC4TS FOREWAN FOREuaN FOREMAN S/S 10/10 2/2 1/1 2/3 10/15 5/7 3/3 i

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VOGTLE PLANT ORGANIZATION Georeia Power ELECTRIC GENERATING PLANT u

UNIT 1 AND UNIT 2 FIGURE 13.1.2-l_(SHEET _2_OF_3).

3405-0

VEGP-ESAR-13 the objectives of the course completed and the course being waived.

If the already completed course of instruction did not meet all required objectives, these additional topics may be taught and course completion may be granted.

e Completion of an examination by the trainee which is equivalent to a course find comprehensive examination.

The examination may be written or oral and must be retained as a record of successful course completion.

13.2.1.1.1 Nuclear Power Plant Theory Training shall be provided in relevant aspects of nuclear power plant theory as required by 10 CFR 55 and NUREG 0737, paragraph k

Theamountoftrainingrequiredis)

I.A.2.1, enclosure 2.

estimated.in tables 13.2.1-1 through 13.2.1-5.

13.2.1.1.2 VEGP Systems f)

Training shall be provided in VEGP systems cr.d precedurectas N,/

required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-5.

13.2.1.1.3 VEGP License and Technical Specifications Training shall be provided in VEGP license and technical specifications as required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-4.

13.2.1.1.4 Fuel Handling and Core Alterations Training shall be provided in-fuel handling and core alterations as required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-4.

13.2.1.1.5 Control Room operations Training shall be provided in control room operations as required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-5.

The training shall be accomplished by utilizing a combination of classroom instruction and hands-on operating practice on the VEGP plant-referenced simulator.

The training will prepare the candidate for the NRC simulator portion of the g

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operating examination.

13.2.1-2 Amend. 16 4/85

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U 14.

Loss of normal feedwater or normal feedwater system failure.

• 15.

Loss of all feedwater (normal and emergency).

16.

Loss of protective system channel.

17.

Mispositioned control rod or rods (or rod drops).

18.

Inability to drive control rods.

19.

Conditions requiring use of emergency boration.

20.

Fuel cladding failure or high activity in reactor coolant or offgas.

21.

Turbino or generator trip.

22.

Malfunction of automatic control system (s) which affects reactivity.

23.

Malfunction of reactor coolant pressure /volumo

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)

control system.

24.

Reactor trip.

25.

Main steam line break (inside or outsido containment).

26.

Nuclear instrumentation failure (s).

B.

Knowledge of Systems Each licensed operator will demonstrato, in the performance of his duties, his satisfactory understanding of the operation of systems and apparatus and his knowledge of operating procedures in each area for which he is licensed.

Any licensed operator who has boon inactive for 4 or more months, before resuming licensed activities, will demonstrato adoquate knowledge of current plant operations.

This shall be accomplished by a review of applicable plant and proceduro changes mado during the period the operator was inactivo, followed by an evaluation by either a cortified instructor on tho VEGP simulator, the superintendent-operatio manager of unit operations, deputy general managor,pp,degonorQfa\\

-an (q) managor.

An unsatisfactory result on the evaluation

% _J 13.2.1-9 Amond. 16 4/85

, _ _ _ - ~ - - _ -. - - -. -. - - - -... - - _. - -

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VEGP-FSAR-13 g

instructor is not involved in the preceding I

requalification program, he may renew his I

certification by preparing for and taking or y nffm 1

conducting a comprehensivevaudit examination.

4' Instructors who fail to complete these annual instructor requalification requirements will not teach integrated plant response to licensed students until they renew their certification.

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(i TABLE 13.2.1-1 (SHEET 3 OF 3)

Minimum Description Type Integral Duration Mitigating core Classroom or 1 day damage self-study Incoro instrumen-tation Excore instrumen-tation Vital instrumen-l tation Primary chemistry Radiation mcnitor-ing Gas generation observation training i

i including walkthrough VFGP Prior to achieving VEGP 3 weeks r

i 20% power 80' VG7/

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After/achiovinge' VEGP 3 months

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20% power Review and audit 1 wook l

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Applicants who have previously boon Nuclear Regulatory Commission licenced or cortified will completo 3 wooks of VEGP walkthrough training.

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Applicants who have previously hold an SRO liconne will not bo requited to completo the 3 months of obnorvation training.

7-y They will completo 3 weekn VEGP walkthrough training instead.

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4 2/84 Amend. 10 9/84 Amend. 16 4/05

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,/S VEGP-FSAR-13 N_)

TABLE 13.2.1-2 (SHEET 1 OF 3)

LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH OTHER THAN PWR LICENSE OR NRC CERTIFICATION (ANY SUPERVISOR OR STAFF POSITION)

Minimum Description Type Integral Duration Nuclear power plant Classroom or 1 week theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and thermody-namics Fluids and matter

~s Fluid statics

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Fluid dynamics

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Heat transfer by conduction, convection, and radiation Change of phase -

boiling Burnout and flow instability Reactor heat transfer limits VEOP systems -and-R Classroom or 4 weeks

-procedures;t self-study Procedures for design and operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications

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VEGP-FSAR-13

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Minimum 1-Description Type Integral Duration l

Reactor safety Cleesr;;r cr1 4 W; he q systems

-self otaff c.

Emergency and reserve systems Containment and shielding Radiation monitoring j

system Auxiliary systems Radioactive waste VEGP license and Classroom or 1 week technical specifi-self-study cations License conditions and limitations Design limitations Fuel handling and Classroem or 3 days i

core alterations self-study i

Facilities and procedures j

Classroom Simulator Control room opera-5 weeks tions (including 100 h General operating X

X VEGP/ simulator) characteristics Specific operating X

X characteristics Load changes X

X i

operating limita-X X

tions Standard, emergency, X

X and plant pro-j cedures Control' manipulation X

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Transients X

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4 2/84 Amend. 10 9/84 Amend. 16 4/85 i

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.r TABLE 13.2.1-5 (SHEET 3 OF 3) l Minimum i

' Description Type Integral Duration i

l Observation training'BS -

VEGP 3 months l

including walkthrough l

training

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Review and audit 1 week

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Prior tofachieving 20 percent applicants for cold licenses j

will complete observation training at a comparable licensed j

commercial nuclear power plant for a period of 6 weeks.

In j

addition, applicants will have at least 6 weeks of VEGP shift experience which includes walkthrough training.

' Amend.- 4 2/84 Amend. 10 9/84 l

0366V Amend. 16 4/85

r"'S VEGP-FSAR-13 (G')

13.2.2 TRAINING FOR NONLICENSED PLANT STAFF The VEGP staff will consist of individuals with significant differences in previous education, training, and experience.

The training programs have been formulated to provide the required training based upon the individual's prior experience.

Personnel will either meet the minimum education and experience recommendation of ANSI /ANS 18.1-1971 or complete a qualification program which will demonstrate their ability to perform the specific tasks.

The' organization conducting the training for the nonlicensed plant staff is the same as that for the licensed plant staff and is shown in figure 13.2.1-1.

13.2.2.1 Training Program A training program has been established for each VEGP organizational group.

At the time of fuel load, personnel assigned to a particular group will complete the initial training before performing independent tasks or will meet the minimum education and experience required by ANSI /ANS 18.1-1971.

The training programs will be the same before and after initial fuel load.

On--thc-j;b-Lz.inin; will-be uscd to (p l'-~\\

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udividuulo fei-thcir accign:d rerpe-cibilitiee.

10, Individual specific training requirements may be waived on a case-by-case basis with adequate justification and approval of the superintendent of nuclear training.

Specific criteria must be met prior to approval of a waiver.

Waivers will be granted only if one of the conditions listed below has been satisfied.

e A previous course of instruction has been completed which contained the name topics and was at least the duration of the course being waived.

The course may have been completed at VEGP or another facility.

For example, a trainee who completes a course'of instruction at Plant Hatch meeting the above criteria would not be required to repeat the course at VEGP.

e A previous course of instruction has been completed which contained all of the objectives of the course being waived.

This would be determined by comparison of the objectives of the course completed and the course being waived.

If the already completed course of instruction did not meet all required objectives, these additional fs topics may be taught and course completion may be granted.

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Completion of an examination by the trainee which is equivalent to a course final comprehensive examination.

The examination may be written or oral and must be retained as a record of successful course completion.

Training prograsms for the following organizational groups have been established:

Health physics / radiochemistry 13.2.2.1.1 Instrumentation and controls 13.2.2.1.2 Mechanical maintenance 13.2.2.1.3 Electrical maintenance 13.2.2.1.4 Shift technical advisor 13.2.2.1.5 Nonlicensed operator 13.2.2.1.6 Licensed operator 13.2.1 Training (instructor qualification) 13.2.2.1.7 General employee training 13.2.2.1.8 Fire team training 13.2.2.1.9 Quality control 13.2.2.1.10 Engineering and technical support 13.2.2.1.11 The syllabus for each training program, including the duration O

and the organizational group receiving the training, is described in the following subsection or paragraphs.

13.2.2.1.1 Health Physics / Radiochemistry Training Program A.

Initial Training Technicians who meet the education and. experience requirements of AN_SI/ANS 18.1-1971 will complete general employee trainingf".proccurizcd water reacter (PPR) %

eysters, balancc c plant (302) syst::c, and mitige*inc e.

-care d mage training normally within 12 months after-t hwuaen L Lv the pccition.", Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific tasks.

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13.2.2-2 Amend 16 4/85

N VEGP-FSAR-13 Approximate Curriculum Outline Duration General employee badge and health 6-10 hi 4 physics training Industrial safety - " - ' " dat 4h New employee fire training 2h 5

General pressurized water reactor 1 week systems General balance of plant systems 1 week Nuclear physics fundamentals 2 weeks Radiation protection 1 week Chemistry fundamentals 1 week Mitigating core damage (commensurate 2h rwith responsibilities)

On-the-job training gl week-B.

Continuing Training One of the following listed programs or other specific programs as requested by the health physics superintendent will be conducted annually.

Personnel who have not completed the offered course will normally g

attend.

Approximate Curriculum Outline Duration' Advanced health physics 1 week Analytical chemistry 1 week Radiochemistry 1 week Corrosion 16 h C.

Annual Requalification Training or Exemption Testing Health physics / chemistry technicians will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

1D.

Initial Foreman Qualifications (and Student Engineers)

Foremen who meet.the-requirements of ANSI /ANS 18.1-1971

- will complete ' General Employee Training 4 P't??, systcm:,*s raining

's andmitigatingccradam]ag BOP cyst==,

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. ce s Duration depends on whether the individual attends additional gg a.

radiation worker training as described-in paragraph 13.2.2.1.8.A.

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described above under initial training #within 12 months 4

-after assignacnt to-the poci44cnA Those who do not meet the ebove requirements must complete initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

E.

Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the health physics superintendent will be presented annually.

Foremen will normally attend these continuing training sessions unless they have already completed the offered course.

F.

Health Physics / Chemistry Supervisor Qualifications and Training The health physics / chemistry supervisors will have the qualifications required of health physics / chemistry foremen and will normally attend a similar continuing training program.

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Incumbents and New Employees s

Personnel with experience that exceeds Nuclear Regulatory Commission (NRC) commitments may fill a position in the career path provided that the health physics / chemistry superintendent certifies that the employee's experience qualifications exceed the position requirements.

The training department may' also accept prior training or experience to fill specific course requirements.

13.2.2.1.2 Instrumentation and Controls Training Program A.

Initial Training Technicians who. meet the education and experience requirements of gSI/ANS 18.1-1971 will complete general employee training & P';?R systems, BGP oyotams, and "

-mitig ting CO&c damagu i.& oluiuy uv&mally within 124

-month: afic& assivhacnt tc the pccition1L Those who do not meet the above requirements must complete initial

. training in order to demonstrate their ability to perform the specific tasks.

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Approximate Curriculum Outline Duration General employee badge and health 6-10 h'd*

physics training Industrial safety end firct aid 2.

4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Process fundamentals 1 week Mitigating core damage (commensurate 2h with responsibilities)

On-the-job training 1 week B.

Continuing Training One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually.

Personnel who have not completed the offered course will normally attend.

Approximate

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Curriculum Outline Duration

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Electronics review 1 week Test equipment 2 days Process instrumentation 1 week Process control systems 1 week C.

Annual Requalification Training or Exemption Testing Instrumentation and controls technicians will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

D.

Initial Foremen Training (and Student Engineers)

Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete Genehal Employee Trainingg,"W" systcas,"

a.

Duration depends on whether the individual attends additional radiation worker training as described in paragraph 13.2.2.'1.8.A.

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described above under initial trainingPhithin 12 months-e efter cacignT.cnt--tc the pccition/s Those who do not meet the above requirements must complete initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

E.

Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually.

Foremen will normally attend these sessions unless they have already completed the offered course.

F.

Instrumentation and Controls Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training s

program.

After initial appointment to the position, i

the new supervisor will complete the following

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training.

s.

Approximate Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including nondestructive testing review)

G.

Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the instrumentation and controls career path, provided the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements.

The training department may also accept prior training or experience to fill specific course requirements.

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4 2/84 13.2.2-6 Amend. 16 4/85 i

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(S 13.2.2.1.3 Mechanical Maintenance Training Program A.

Initial Training Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will f

completegeneralemployeetraining((Phmsystems, and BOP 4 gnd'an-Yde-J,f

+ystamn training narmally 'fithin 1_ months af tcrt frata,> p ? ! dMCr,gdeseignm:nt to the position." Those who do not meet the above requirements must complete initial training in 64/W f# b b' order.to demonstrate.their ability to perform the asu p 3 rvJer*d specific tasks.

48

Approximate Curriculum Outline Duration General employee badge training 6-10 h'd*

Industrial safety-and first aidt; 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Maintenance fundamentals 1 week

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Mechanical fundamentals 1 week s

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On-the-job training 1 week t

B.

Continuing Training One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually.

Personnel who have not l

completed the offered course will normally attend.

Approximate Curriculum Outline Duration Theory and maintenance of pumps 1 week and valves Power transmission devices 2 days Shop fundamentals 1 week Crane safety and operation 3 days Shaft alignment 2 days Motor-operated valves 3 days a.

Duration depends on.whether the. individual attends additional gss l

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radiation working < training as described in paragraph C-13.2.2.1.8.A.

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C.

Annual Requalification Training or Exemption Testing Mechanics will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures, D.

Initial Foremen Training (and Student Engineers)

Foremen who meet the requirements of ANSI /ANS 18.1-1971 g p $.

'will complete General Employee Trainingg &1R cyctcmc,R

-end BOP cyctcm3 training Oc dcccribedenbove under l-fc A Th} M d8 #

, initial training,within 12 monthc cfter cccignmen W T-the-peeihona Those who do not meet the above I,,y 4 gerfarw requirements must complete initial training and progress I^d*f** ""

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through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

E.

Continuing Foremen Training One of the listed continuing training programs or other

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j specific programs as requested by the maintenance

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superintendent will be presented annually.

Foremen will normally attend those continuing training programs unless they have completed the offered course.

F.

Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program.

After initial appointment to the position, the new supervisor will complete the following training.

Approximate Curriculum Outline Duration Electrical, pressure vessel) and 3 days piping codes and standards (including nondestructive _ testing review)

G.

Incumbents and New Employees i

Personnel with experience that exceeds NRC commitments g-'s may fill a position in the mechanical career path i

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provided that the maintenance superintendent certifies

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that the employee's experience qualifications exceed 1

13.2.2-8 Amend. 16 4/85 l

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VEGP-FSAR-13 V

the position requirements.

The training department may also accept prior training or experience to fill specific course requirements.

13.2.2.1.4 Electrical Maintenance Training Program A.

Initial Training Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will p s[ q Y/e,-Je complete general employee trainingsg NR systems, and DOF {

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'assignT.cnt te the pceiticavA Those who do not meet the

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above requirements must complete initial training in 4g,.,,/,3g,,u,Q, brder to demonstrate their ability to perform the specific tasks.

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Approximate Curriculum Outline Duration General employee badge training 6-10h'kl Industrial safety and firct aid 0 4h

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New employee fire training 2h

(

General pressurized water reactor 1 week systems General balance of plant systems 1 week Maintenance fundamentals 1 week Direct current fundamentals 1 week Alternating current fundamentals 2 weeks Electrical safety, drawings, and 1 week test equipment On-the-job training 1 week B.

Continuing Training One of the following listed programs or other specific programs as requested by the maintenance superintendent will be. conducted annually.

Personnel who have not

. completed the offered course will normally attend.

a.

Duration depends on whether the individual attends additional radiation worker training as described in paragraph 13.2.2.1.8.A.

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I f 'N VEGP-FSAR-13 Approximate Curriculum Outline Duration Protection devices, control devices, 3 days and motor control centers ac/dc motors and generators 4 days Solid state theory 3 days i

Batteries, chargers, and inverters 1 day Pyrotronics fire detectors 1 day Motor-operated valve maintenance 1 day Switchgear and breaker maintenance 3 days Amp lugging 1 day C.

Annual Requalification Training or Exemption-Testing Electricians will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

D.

Initial Foremen Qualifications (and Student Engineers) m Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete general employee traininggg"'#R systcmc,(

cnd BOP cyctc=c trcining er described a-cyc undcr-C an O n-YgeJob

-initial Laining within 12 mcnths after assignacnt tc %

] g 3h ag dese.e,-le/ -the pccition.

Those who do not meet the above a

requirements must complete initial training and progress

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through most of the continuing training courses in order e

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g, geTre to demonstrate their ability'to perform the specific perfsrm>} b C1*b d.

E.

Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually.

Foremen will normally attend continuing training programs unless they have previously completed the offered course.

f GL F.

Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program.

After initial appointment to the position g the new supervisor will complete the following

~

training.

(p)

V 13.2.2-10 Amend. 16 4/85 j

/~'s VEGP-FSAR-13 i

\\

V Approximate Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including nondestructive testing review)

G.

Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the electrical career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements.

The training department may also' accept prior training or experience to fill specific course requirements.

13.2.2.1.5 Shift Technical Advisor Training Program A.

Education Requirements A'

/

Shift technical advisors will have a bachelor's degree in a scientific or engineering discipline.

B.

Training Program The candidate holds or has held an NRC senior re' actor operators license for that type of reactor, or the candidate completes a Georgia Power Company (GPC) shift technical advisor training program described in 1% sim SW '** c'A */ "'Ye table 13.2.2-1. Ls erhler-case fm ra in yle enf ense art / anel sis of uc s

Y m /* fa,,y f, fra a s;,, h &

C.

Exper en.ce Requirements-The candidate will have 1 year of power plant experience and will have performed reactor operator or senior-reactor operator duties for that type of reactor, or the candidate will receive 1 month of on-the-job training as an extra shift technical advisor.

D.

Requalification Training for Shift Technical Advisors Shift technical advisors will attend the same requalification program as NRC-licensed operators.

Persons not actively performing the shift technical advisor functions for a period of 4 months or longer

~g shall, prior to assuming responsibilities of the

)

position, as a minimum receive training to ensure they s_ /

are cognizant of facility / procedure changes that occurred during their absences.

13.2.2-11 Amend. 16 4/85

'N VEGP-FSAR-13 q

Persons not performing the shift technical advisor function for a period of 6 months or longer shall, prior to assuming the responsibilities of the position, undergo an individual requalification program.

13.2.2.1.6 Nonlicensed Operator Training Program A.

Initial Training After the start of fuel load, all personnel-assigned to perform independent plant equipment manipulations will either complete this initial training program, be qualified to the shift. technical advisor level or certified to the senior reactor operator level, or have experience which is equivalent to the following program.

4 Approximate Curriculum Outline Duration General employee badge and health 6-10 h'3' physics training

[

Industrial safety-ar.d first e id 'L 4h i

New employee fire training 2h l

Nuclear power plant fundamentals 1 week j

Power plant components 1 week j

VEGP systems 4 weeks On-the-job training 1 week B.

Continuing Training After completing initial qualifications, the nonlicensed operator will complete qualification on the plant systems on which he was not initially qualified.

Normally, the nonlicensed operator will qualify on all systems outside the control room and containment during-the individual's first 3 years in the plant operations department.

d C.

Annual Requalification Training or Exemption Testing Nonlicensed operators will complete annual requalification training or exemption testing to.make them aware of and review important changes made to plant emergency, radiation protection, security, and respirator procedures.

i l

\\s Amend.

3 1/84

- (, /u _,sp

(

Amend.

4 2/84 v

0 13.2.2-12 Amend. 16 4/85

x VEGP-FSAR-13 I

)j D.

Nonlicensed' Operator Progression After completing a license training program, many operators will progress to licensed positions.

The

)

licensed training programs are described in subsection 13.2.1.

13.2.2.1.7 Instructor Qualification Program and Certified Instructor Requalification Program This program has been outlined in paragraph 13.2.1.3.3 for all training instructors.

In addition to these requirements, the fire protection training instructor shall also meet the requirements outlined in paragraphs 13.2.2.1.9.D and 98.C.3.d(2).

13.2.2.1.8 General Employee Training (Badge Training)

A.

General Training All personnel +hy lt No'*ry far'*'tsel int /ud'i who are granted unescorted access to 4 dure

,s VEGP's protected area will receive the following

(

)

training or, if they have completed a similar program at another plant or facility, will be tested to verify satisfactory knowledge of VEGP procedures.

Approximate Curriculum Outline Duration General descriptior,of VEGP 4h facilities, general VEGP procedures and instructions, station emergency plans, industrial safety program, fire protection program, security program, and quality assurance program i

Ybb(

a,.

Duration depends on whether the individual attends additional radiation worker training as described in paragraph 13.2.2.1.8.A.

Amend.

4 2/84 13.2.2-13 Amend. 16 4/85

1

,Q VEGP-FGt,2-13 s

. Radiation health and safety 2h will meet the intent of Regulatory Guide 8.8 for personnel who enter restricted areas.

3 Regulatory Guide 8.27 and 8.29 are

\\

being used to develop the T

radiation protection portion of general employee training.

Material discussed in Regulatory

-Guide 8.29, Appendix A, will be covered except for Sections 17, 18, 22, 23, 24, 28, 29, and 31, since these sections would be of little value to personnel in determining their risk from exposure to occupational radiation.

p-

~

' Approximate d(

6 lum Out Duration Radiation worker training 4h Additional radiation work

,g

(

)

practices training will be x_f provided for those personnel who are required to work in radiation-controlled areas without escort.

Respiratory protection training 2h for personnel required to work in areas of high airborne radioactivity concentration.

1 B.

Annual Exemption Testing All personnel will complete annual requalification training or exemption testing to ensure that they have retained satisfactory knowledge of VEGP procedures.

13.2.2.1.9 Fire Brigade Training A.

Initial' Training Personnel assigned to any fire brigade will complete training in the following areas as designated by ESAR appendix 13B before being assigned as active brigade members.

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V 13.2.2-14 Amend. 16 4/85 i

l I

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~

VEGP-FSAR-13 E.

General Employee Fire Training Fire protection training for plant employees who are allowed unescourted access will include instructions in the following areas:

1.

Appropriate fire protection administrative controls.

2.

Fire barrier and fire barrier penetration seals.

3.

Response to fire alarms.

4.

Action and responsibility upon discovery of fires.

The capability to evacuate the plant facilities will be evaluated annually.

This evaluation may be conducted coincidentally with emergency plan exercises or drills.

'T 13.2.2.1.10 Quality Control Training Program i

-A.

Initial Training s

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Quality control inspectors who meet the requirements to

.be certified Level I in accordance with ANSI N45.2.6-1978 will complete general employee training as described below.

Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific tasks.

Approximate Curriculum Outline Duration General employee badge training 6h Industrial safety-and first tid E 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Quality control codes, standards, 3 days and procedures Visual inspection 1 week

('~')T

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13.2.2-17 Amend. 16 4/85

.~

C(

VEGP-FSAR-13 d

B.

Continuing Training After completing initial qualification, quality control personnel will usually attend annually a program to improve their quality control skills or a program from the electrical, mechanical, or instrumentation and controls schools.

C.

Annual Requalification Training or Exemption Testing Quality control specialists will complete annual requalification training or exemption testing to review important changes to plant emergency, radiation protection, security, and respirator procedures.

D.

Incumbe:nts and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the quality control career path provided the general manager certifies that the employee's experience qualifications exceed the position requirements.

The training department may g-

.also accept prior training or experience to fill

/

specific course requirements.

13.2.2.1.11 Engineering and Technical Support A~.

Initial Orientation Training Professional personnel who do not have prior nuclear

. power. plant experience will complete the following orientation program normally during the first 6 months at VEGP.

Approximate Curriculum Outline Duration General employee badge and health.

6h physics training.

l Industrial safety and fir:t aide 4h New employee fire training 2h Reactor theory, health physics,-

1 day and primary systems i

Primary systems, emergency systems, 1 day heat removal systems, and radiation waste and monitoring systems 13.2.2-18 Amend.-16 4/85 i

t

'N VEGP-FSAR-13 dob 13.2.2.4 Initial Position %ek Analysis j0b The training programs d scribed in section 13.2 are the result of the initial position analysis for VEGP staffing.

The training organization will use a combination of plant equipment reviews ~by instructors, training committee reviews by plant supervisors, and instruction reviews by students to obtain f

feedback to update our training plans or the position-t&sk c_ qab

+

analysis.

Georgia Power Company stresses the use. of this feedback to meet our overall training objective to train for job proficiency.

13.2.2.5 Training Program Syllabus The VEGP training organization is described in subsection 13.2.1 and figure 13.2.1-1.

Georgia Power Company will use the same training programs to qualify its personnel both before and after the initial fuel loading.

Almost all programs in this section are considered formal or " classroom" programs.

A formal program consists of instruction in the classroon, laboratory, simulator, and field which is supervised by an instructor.

Specifically, the shift technical advisor program

~3i (paragraph 13.2.2.1.5) and the training (instructor s_,/

qualification) program (paragraph 13.2.2.1.7) use some on-the-job training before the individuals in these organizational groups are permitted to perform job tasks.

13.2.2.6 Reactor Operations Experience Training i

Reactor operations experience training will be provided as outlined in paragraph 13.2.1.2 by using the VEGP simulator, preoperational test program, and observation of other light-water reactors.

13.2.2.7 Differences in Training Programs The difference in the training programs for individuals based on the extent of previous nuclear power plant experience is described in paragraph 13.2.2.1.

13.2.2.8' Fire Protection Training Program A description of the fire protection training program used for fire brigade members is described in paragraph 13.2.2.1.9.

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l 13.2.2-20 i

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fN VEGP-FSAR-13 0

13.2.2.9 Training Program Effectiveness Training program effectiveness is evaluated by either written,

-oral, or practiced demonstration examinations for each employee.

Figure 13.2.2-1 is a schedule showing the start of each portion of the nonlicensed plant staff training program in relation to the schedule for preoperation tests, fuel load, and expected time for license examination.

Since all of the training programs in this section are used for both units before and after fuel load, after a particular program is started, that

~

program will be available for use any time there is a need to qualify additional personnel.

At the time of fuel load, sufficient VEGP personnel will be qualified in each organizational group to meet the staffing requirements of l

subsection 13.1.2.

If fuel loading is delayed, the continuing and requalification 4

training programs as described in this subsection will be implemented to ensure personnel job proficiency.

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