ML20202A889

Forwards Proposed Changes to FSAR Section 13.2, Training. Changes Result from Insp Repts 50-424/85-45 & 50-424/85-51 Which Addressed Concerns Associated W/Readiness Review Module 2, Training & Qualification Program

ML20202A889
Person / Time
Site:	Vogtle
Issue date:	04/04/1986
From:	Bailey J GEORGIA POWER CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
GN-862, NUDOCS 8604110081
Download: ML20202A889 (83)

Text

{{#Wiki_filter:__ - Georgia Power Corrpany Route 2. Box 299A Waynesboro. Georgia 30830 Telephone 404 554 9%1 404 724-8114 Southem Company Services, Inc Post Office Box 2625 Birmingham. Alabama 35202 Telephone 205 870-6011 Vogtle Project April 4, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log: GN-862 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 TRAINING FOR LICENSED OPERATOR AND NONLICENSED PLANT STAFF

Dear Mr. Denton:

Attached for your staff's review are proposed changes to FSAR Section 13.2. These changes are a result of NRC Region II inspection reports 50-424/85-454 and 50-424/85-51 which addressed NRC concerns associated with Readiness Review Module 2, Training and Qualification Programs. If your staff requires any additional information, please do not hesitate to contact me. Sincerely, l .h. J. A. Bailey Project Licensing Manager JAB /sm Attachment xc: R. E. Conway G. Bockhold, Jr. R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2) L. T. Gucwa B. Jones, Esquire Vogtle Project File 0424V C604110001 860404 I\\ PDR ADOCK 05000424 C PDR

3 VEGP-FnAP-13 13.2 TRAINING 13.2.1 LICENSED OPERATOR TRAINING The VEGP licensed staff will consist of individuals with significant differences in previous education, training, and experience. The licensed training programs have been formulated to provide the required training based upon the individual's prior experience. These programs are designed to provide the highest degree of operator proficiency by effectively using the VEGP simulator. ^ 13.2.1.1 Trainin,g Program _s The details of typical' training programs, including syllabus, duration, classroom, and on-the-job training, are contained in tables 13.2.1-1 through 13.2.1-6. The programs described in l19 these tables will remain the same for both units before and after initial fuel loadingu.n/ess s // gd, These programs are designed to train personnel with various backgrounds as indicated in the above tables. These tables 16 include position, titles, and experience of the individual. The VECP training department is responsible for the coordination of teaching courses and supervising the instruction. The VEG? training department is shown in figure 13.2.1-1. The qualificaticns.of instructors and a description. of the instructor requalification program are found in caragraph 13.2.1.3.3. I nd i'/1du a l specific training requirements may be waived on a

ase-by-case basis with adequate justificntion and approval ot the superintendent of nuclear training.

Specific criteria must be met prior to approval of a waiver. Waivers wil.1 be granted only if one of the conditions listed below has been satisfied. A previous course of instruction has been completed o which contained the same topics and wasy 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. o A previcus course of instruction has been completed which contained all of the objectives of the course being waived. This would be determined by comparison of Amend. 16 4/85 13.2.1-1 Amend. 19 9/85

1 VECP-FSAR-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. gggj o Completion of an examination by the trainee which is equivalent to a course teed 3 comprehensive examination. The examination may be written or oral and must be retained as a recora of successful course completion. 13.2.1.1.1 Nuclear Power Plant Theory Trainir.g shall be provided in relevant aspects of nuclear power plant theory as required by 10 CFR 55 and NUREG 0737, paragraph I.A.2.1, enclosure 2. The amount of training required is estimated in tables 13.2.1-1 through 13.2.1-6. l 13.2.1.1.2 VEGP Systems and Procedures Training shall be provided in VEGP systems as required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-6. DELETE 7 13.2.1.1.3 VEGP License and Technical Specifications 16 t 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 13.2.1-5. 13.2.1.1.4 Fuel Handling and Core Alterations l f Training shall be provided in fuel handling and core alterations as required by 10 CFR 55, as indicated in tables 13.2.1-1 (_thraugh 13.2.1-5. 3 13.2.1.1.jf 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 13.2.1-6. The training shall be accomplished by utilizing a combination of classroom instruction and hands-on operating practice on the VEGP plant-referenced simulator. The traintng will prepare the candidate for the NRC simulator portion of the operating examination. Amend. 16 4/85 13.2.1-2 Amend. 19 9/85

For & purges cf fAs haMn v AE six weeks skal1 be.deSkd ss LIG k ws of pafie- ;,, ae,. u [! & apisat-g Cix calendse weeks % s* VEGF-ESAF 3 Y i 13.2.1.1./ Mitigating Core Damage Training for mitigating core damage will have the course content as described in NUREG-0737, item II.B.4, and will be taught during the courses scheduled in the syllabus, as shown 19 \\ in tables 13.2.1-1 through 13.2.1-6. 5 33.2.1.1.)I Hot Participation /Cbservation and Walkthrough Training ) The following paragraphs define the meaning of the terms het participation experience, observation training, and walkthrough training. Approximate duration for these types of training ar l19 specified in tables 13.2.1-1 through 13.2.1-6. The training will prepare the license applicants for the plant walkthrough portion of Nuclear Regulatory License examination.g Hot participation experience is direct involvement in review and discussions leading to decisions relative to operation of a commercial nuclear power plant, or direct hands-on operation as a trainee at a commercial nuclear power plant. Hot participation experience requirements apply only prior to VEGP achieving 20 percent power. 16 Observation training constitutes assignment to an operating shift for the purpose of training. Emphasis is placed on observinq sis many shift activities as p."srible, e.g., shift relief, operator rounds, local equipment operations, control room activities. Hands on participation may be conducted under t r a i - i "'M by

• he observation of a qualified operator.

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?" ra *-nt pr**^"- Waikthrough training is a systematic program to become familiar with plant equipment and layout. It may be conducted concurrently with observation training or may be conducted as a separate program. b l 13.2.1.1 d Review and Audit j A short ysriod of time will be allocated for each individual license candidate to review material and prepare for a comprehensive audit examination. The effectiveness of the training program in the case of each trainee will be evaluated / from the results of a series of written, oral, and manipulation examinations. Applicants for Nuclear Regulatory Commission (NRC) license examinations are given an audit examination which has the same structure as the NRC examination, including a VECP simulator examination. Since applications for license must be made before the audit examination results are usually available, Amend. 16 4/85 13.2.1-3 Amend. 19 9/85

VECF-FS.:: _3 Georgia Power Company (CPC) will certify to the extensive operating experience based upon the individual's satisfactory progress in the training program. If the individual falls to demonstrate the ability to pass an audit examination or the 3 ability to properly manipulate VEGP simulator controls, GPC will request that the NRC not administer an examination to this individual. Occisionally, the audit examin t'on may uncover a weak area in an individual's knowledge, GPC belte"es that the individual has sufficient time to correct the problemj , ' ' n t i r. d e_*1 n 9 "- -_G A:,re 9e m / " Y yYec f,f at c: =Ng' 4J u mMa,,Ah}dn wiff ng g a an a> d &,;4;,,y re~tNIudi** ky ysnt, cerfi absen W. djen 13.2.1).1 8 r' n y7 Operator Training Schedule The bar chart in figure 13.2.1-2 shows the schedule of the licensed operator training program in relation to the schedule for preoperational tests, fuel load, criticality, and the expected time for license examinations. If fuel loading is significantly delayed, the VEGP license requalification program will be used to maintain. operator proficiency. Several specific training i tem.s for licenned operators identified in tables 13.2.1-1 through 13.2.1-6 (and included in l general topic format in figure 13.2.1-2) will be taught just prior to the precritical license examinations. The items not yet included as a part of training, but to be taught prior to licensing include: o VEGP Gperating Procedures VEGP Fuel Handling and Core Alteration o o Mitigating Core Damage VEGP walkthrough Training o o Reactor Startup (if required by Section 13.2.1.2) Plant Walkthrough Audit Exam o Personnel listed on figure 13.2.1-2 without an asterisk have completed training in the time frames indicated with the exception of items listed above. 13.2.1.2 Oper_atio_n Experi,ence Reactor operations experience training will be provided by the VEGP plant-specific simulator, the experience gained from the VEGP staff participating in the preoperational test program, and the experience received by the VEGP staff observing and participating in plant startup or operations of other light-Amend. 3 1/84 Amend. 16 4/85 13.2.1-4 Amend. 19 9/85

S VEGP-FSAR-13 water reactors. The cold license training program will also contain a program of 10 reactor startups on a research/ test type reactor to gain actual "at the controls" experience. Personnel with prior Navy nuclear experience as an engineering watch officer, engineering watch supervisor, reactor operator, or other equivalent positions or those who have prior commercial nuclear plant licensed operator experience or those who have prior test reactor e:tperience shall be exempted from 10 reactor 10 startup requirements. A combination of the preceding will satisfy the experience requirements of NUREG-0737, items I.A.2.1. The details of the simulator program are contained in tables 13.2.1-1through13.2.1-{. 6 The VEGP simulator will conform to the guidance given in Regulatory Guide 1.149. Performance testing of the simulator specified in paragraph 5.4 of ANSI /ANS-3.5-1981 will be accomplished in the following manner: 1. Comparison of the steady state operating values of critical and noncritical parameters between the VEGP Unit 1 control room and the simulator at various power levels. 2. Maneuvering of the simulator through the following 16 plant evolutions listed in paragraph 3.1.1 of the standard. -A. Plant startup - cold to hot standby. The starting conditions shall be refueling conditions of temperature and pressure. 17 B. Nuclear startup from hot standby to rated power. C. Turbine startup and generator synchronization. D. Reactor trip followed by recovery to rated power. E. Operations at hot standby. F. Load changes (manual and automatic control). I G. Plant shutdown from rated power to hot standby to cooldown to cold (refueling) conditions. H. Startup, shutdown, and power operations with less than full reactor coolant flow is not permitted by the VEGP operating license and therefore will not be conducted. Amend. 10 9/84 Amend. 16 4/85 13.2.1-5 Amend. 17 7/85

a VEGP-ESAR-13 3. Core physics testing will be comprised of an evaluation of simulation of: A. Estimated critical position computation. B. Estimated critical concentration computation. C. Shutdown margin computation. D. Estimating criticality by the I/M plotting method. 4. Operations surveillance procedure testing will be comprised of those control rcom operations which are required to conduct the operability tests of the following systems: A. Diesel generators. B. Auxiliary feedwater. hsrd C. High dannb safety injection. D. Safety injection. E. Residual heat removal. 17, F. Nuclear service cooling water. 5. Simulator malfunction conditions shall be evaluated by . experienced staff members for best estimate response or compared to actual plant data or other best estimate data. 6. The simulators response to transient conditions will be compared to design information from the simulator data base or other best estimate data. 7. When a limited change is made, a specific performance test on the affected systems and components shall be performed. All }'esting will be performed independently from any classroom activity, with testing cf the simulator as the only objective. The results of all testing will be documented as the testing is being perforned. Factory acceptance testing of the VEGP simulator has already been completed. The performance test described above will be completed prior to August 1, le38 and not less than every 4 years thereafter. 13.2.1-Sa Amend. 17 7/85 f e

G VEGP-FSAR-13 13.2.1.3 Qualification and Regualification Program The qualification and requalification program for licensed operators and the training department is described in the following paragraphs. 16 13.2.1.3.1 Licensed Operator Qualification Reactor operator and senior reactor operator training programs include the qualification requirements contained in NUREG-0737, ) item I.A.2.1, and are described in tables 13.2.1-1 through l19 13.2.1-6. Amend. 16 4/85 Amend. 17 7/85 13.2.1-Sb Amend. 19 9/85

VEGP-FSAR-13 13.2.1.3.2 Licensed Operator Requalification Program The licensed operator requalification training program will be implemented within 3 months after issuance of an operating license. The program shall be continuous and may be conducted as an intensive program of several weeks duration each year or may be spaced out over a period of up to 24 months, with elements of the program occurring on a periodic basis. Records of the requalification program shall be maintained for a period of 2 years from the date of the recorded event to document the participation of each licensed operator or senior operator in the requalification program. The records shall contain copies of written examinations administered, the answers given by the licensee, results of evaluations, and documentation of any additional training administered in areas in which an operator or senior operator has exhibited deficiencies. An ~ original or reproduced copy or microfilm copy will fulfill these record retention requirements. The reproduced copy or microfilm copy will be authenticated by authorized personnel and will be capable of producing a clear and le,pible copy after storage for a period of 2 years. For-u.efoses el H,ese freyrwne, Amual shall be delg*nej U

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Idennis) &l he &* k U ence y e A. cn/enbtr n 13.2.1.3.2.1 Classroom Study. A planned lecture series will Jk be presented annually (i.e., each calendar year) covering those i subjects where training feedback indicates a need for ~ additional training. The lecture series will be based on the following subjects as outlined in 10 CFR 55. A. Theory and principles. B. General and specific plant operating characteristics. C. Plant instruments and controls. D. Plant protection systems. E. Engineered safety systems. F. Procedures. G. Radiation control and safety. H. Technical specifications. I. Applicable portions of 10 CFR. 13.2.1-6 Amend. 16 4/85

7 VEGP-FSAR-13 J. Quality assurance for operations. K. Major upcoming events. L. Heat transfer, fluid flow, and thermodynamics. 1. 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. M. Mitigation of accidents involving a degraded core. 1. Incore instrumentation. 2. Excore instrumentation. 3. Vital instrumentation. 4. Primary chemistry. 5. Radiation monitoring. 6. Gas generation. 13.2.1.3.2.2 On-the-Job Training. A. Reactivity Controls Each licensed operator will, during the term of his license, perform a minimum of 10 reactivity control manipulations in a combination of reactor startups, l reactor shutdowns, or other control manipulations which demonstrate his skill and/or familiarity with reactivity control systems. Each senior reactor operator shall direct or evaluate the activities of at least 10 control manipulations during his license term. These control manipulations will normally be performed on the VEGP simulator. 13.2.1-7 Amend. 16 4/85

VEGP-ESAR-13 The following control manipulations and plant evolutions are acceptable for meeting the reactivity control manipulations required by Appendix A, Paragraph 3.a., of 10 CFR 55. The starred items shall be performed on an annual basis (once each calendar year); E all other items shall be performed on a 2-year cycle (once each 2 calendar years).

• l.

Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established. 2. Plant shutdown. +3. Manual control of steam generators and/or feedwater during startup and shutdown. 4. Boration and/or dilution during power operation.

• S.

Any significant (10 percent) power changes in manual rod control. 16

• 6.

Loss of coolant including: a. Significant pressurized water reactor (PWR) steam generator leaks. b. Inside and outside primary containment. c. Large and small, including leak rate determination. d. Saturated reactor coolant response. 7. Loss of instrument air. 8. Loss of electrical power (and/or degraded power sources).

• 9.

Loss of cote coolant flow / natural circulation. 10. Loss of condenser vacuum. 11. Loss of service water. 12. Loss of shutdown cooling. 13. Loss of component cooling system or cooling to an individual component. Amend. 10 9/84 13.2.1-8 Amend. 16 4/85

f* VEGP-FSAR-13 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. Turbine or generator trip. 22. Malfunction of automatic control system (s) which affects reactivity. ( i 23. Malfunction of reactor coolant pressure / volume control system. 1 24. Reactor trip. 25. Main steam line break (inside or outside containment). 26. Nuclear instrumentation failure (s). B. Knowledge of Systems Each licensed operator will demonstrate, 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 been inactive for 4 or more months, before resuming licensed activities, will demonstrate adequate knowledge of current plant operations. This shall be accomplished by a review of applicable plant and procedure changes made during the period the operator was inactive, followed by an evaluation by either a certified instructor on the ('",. VEGP simulator, the superintendent-operations, manager of unit operations, deputy general manager, or general manager.jg n unsatisfactory result on the evaluation A Prior b + bis enk% ik Hu sidl k ndihl for. g g c l,d133.1-9e sban I,au presay cowred w [ Amend. 16 4/85

VEGP-ESAR-13 shall require the operator to have on-the-job training in areas determined as weak. To remain on active status, a reactor operator or senior reactor operator is required to have a minimum of 8 h/ quarter active carticipation in operation of the plant,@ the VEGP simulato % C. Plant Changes Each licensed operator will be kept informed of significant plant design changes, procedure changes, and license changes. Changes of a magnitude requiring detailed explanation will be reviewed by special instruction with 100 percent participation of licensed personnel. D. Procedures Each licensed operator will review abnormal and emergency procedures at a minimum of once per calendar year. Failure to complete a procedure review will require that the licensee be removed from license lj duties until such review is completed. 13.2.1.3.2.3 Evaluation. A. Observation The performance of licensed operators will be evaluated annually by operating supervision or by a certified instructor usually on the VEGP simulator. This shall include evaluation of actions taken or to be taken during actual or simulated abnormal or emergency conditions. Observation reports are required for personnel (supervisory and nonsupervisory) who hold an NRC license _ with the exception of (the superintendent-operations, manager of (unit operations, deouty general manager,_or general (manage r, andfcertified simulator instructors. B. Annual Examinations Annual written examinations will be given to all licensed personnel to determine areas in which requalification training is needed. These examinations are normally evaluated within 30 days (2 months for unusual conditions with corporate office approval). A minimum grade of 80 percent correct on any section shall exempt an operator or senior l operator from required attendance at requalification l 13.2.1-10. Amend. 16 4/85 \\

VEGP-FSAR-13 lectures pertinent to that section. Any section grade less than 80 percent but greater than 70 percent will require attendance at requalification lectures pertinent to that section within 12 months from the examination date. An overall grade of less than 80 percent correct on an annual written examination, a section grade of less than 70 percent, or an unsatisfactory performance evaluation will require an operator or senior operator to be relieved of licensed duties so that he may participate in an accelerated requalification program. This will be documented with written notification to the individual and to the appropriate department head. An operator or senior operator who has been relieved may return to his licensed duties following completion of accelerated requalification training in areas where he was weak, including a grade of not less than 80 percent correct on examinations given over such areas. The NRC may participate in the annual examination process. Annual examinations will be given at the conclusion of the requalification training program so 16 as to measure the overall effectiveness of the complete program and not to disrupt shift manning and training schedules. C. Lecture Examinations Writt n enamin.* ions w 11 be iven to individuals who recei d 1 ss t n 80 rcent ,n th pertit nt section \\1 f the nn 1 exa inatio cove 'ng m terial resented the ogr - lec ure s ies. gra e of it a than Box erce on ny r ire lectu se 'es exa ' nation KEE . al re re lice ed o rator to b resche led f 3t iti al i stru ion d tes ing that bject ggg wi in'\\ e n xt 3 mont Tl* 3 mc ths ty be l3.1. l.3.1.1.C exte eAyt le 9th tim fa ref eling o tage ( falli w\\s hin-that eri L.ture pres nted fo informa to f ajor pco ng e.nts nd/o plant ica on ma be ocum ted y att ndan recor 13.2.1.3.3 Instructor Qualification and Requalification Program The qualification and requalification program for instructors as described below includes requirements of NUREG-0737, item I.A.2.3. This program'will be fully implemented prior to fuel load. 13.2.1-11 Amend. 16 4/85

/d ATTAc#4Ev7 /3.2./.3.2 3.c-s4 su NYib e+1 eXUnir) iof1s W $ he Jiherfoffnb5// Covery mderal aseded in Be proywn ted-svies. A p yde oF /ess L 80 pwed on uy ledm series e a,,dik, 4 di La eeviewd and avJuded. 7%is enfadion will be based on de. score received ad mderkt n,issed. ANec eudadion, f4e lacrised eh y wilt le sdredded An addi&J aidruck a>rd edediny wh Gree inodds. liilare h meeHAe .s a s a s g. a s -

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VE37-FSAF-13 A. Initial Qualification The training department will use a qualification checklist to establish the initial qualification requirements for all new instructors and for 7 instructors whose teaching responsibilities are going to significantly change. These special qualificaticn checklists shall.nc1'ide the following requircrents 1. The instructor's. supervisor will review r.h e employee's background and establish qualification goals and qualification deadlines. Beside.s other qualifications, the following minimum goals will be established: a. For new instructors who do not have a classroom teaching background, the empicyee l will have to present a lecture to a group of i experienced instructors before lecturing plant students. The company's instructor course as a minimum shall satisfy this requirement. l b.4 .o

nstructors who teach licensed s_udents, 16 1

before the new instructor conducts a comprehensive program, the employee will meet 8 NRC requirements by cbtaining the appropriate [ certification. This requirement does not P prevent nonce,rtified members of the training sta:f from teaching licensed personnel in the 'nstruc*.or's area of expertise. 2. The superintendent-nuclear training shall approve the qualification checklist At the time or 1, o s; 7 and shall approve the final qualification of each instructor. Before these instruct 3Ti~ceach systems, integrate response, transients, and cimulator courses to licensed operators, they will demonstrate their competence by successful completion of a senior reactor operator xamination.A} _ ~ B. Certified Instructor Requalification l Licensed or certified instructors will complete the requirements of the licensed operator requalification program annually by teaching, performing, or taking ) examinations for each required element of the requalification program. Conducting simulator l training will be considered the same as nupervising license dutieb in the plant control room. If an of flie li["5'M h *p,jnj p.pdorf wke are Amend. 7 5/04 N00 g-g not re d e me d[ m,,y 4 MM d/[ fg/ ar c Amend. 16 4/85 I w5 12 Amend. 19 9/85 ey s on pwkeuke subjech sul, as a,ere w d,ayedf5.sie-n chemi&y,de, may kmod unics Leal esf ledur p 1

l VEGP-FSAR-13 [nstructorisnot involved in the preceding l requalification program, he may renew his certification by preparing for and taking or lg conducting a_ comprehensive written audit examination. instructors who fail to complete these annual instructor requalification requirements will not teach integrated plant response to licensed students until they renew their certification. An fl,3f.yor m. ,.g,,4 w bis CekYksllN bf riVitWI'y' flIt /k. con /a5> fn h);c repMdim ycyan ud kkiy a. 6,,p, hensive wi.1% entom. bN 5wM d a^.e. W ' -d'" %W v k +L egLd. & Au uuaes - orgr 1% IA. 93 % em 5 e k &a &s s ' 4 i a a \\ JA. l l l l l I r i 01 A Att 11 7 1.11 h avia n et 1A A / D C.

/s VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH COMMERCIAL PWR LICENSE OR NRC CERTIFICATION O (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-l10 namics l Fluids and matter II Fluid statics 4 Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase boiling Burnout and flow instability Reactor heat transfer limits VEGP systems Classroom or 1 week self-study Procedures for design and operating changes Reactor coolant system mechanical design y Reactivity control mechanisms and indications Reactor safety systems Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 )

13 VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 2 OF 3) Minimum Description Type Integral Duration Emergency and reserve systems Containment and shielding Radiation monitoring system gg g,y,,f,/ Auxiliary systems

• '&ECT A

Radicactive A^-- b CP license and - Classroom or 1 technical specifi-self-study cations License conditions jg-pj((gIE and limitations Design limitations 4 1 Fuel handling and Classroom or 3 days core alterations self-study: Facilities and procedures I Classroom Simulator ' Control room opera-4 weeks tions (including 80 h General operating X X VEGP/ simulator) characteristics { Specific operating X X characteristics Load changes X X operating limita-X X f tions Standard, emergency, X X and plant pro-cedures Control manipulation Transients X e Amend. 4 2/84 Amend. 16 4/85

/4 l 11TTAchlHERT 13.1.l-l Fuel handling and v ' core alterations Facilities and procedures ~ ~ Classroom Simulator q Control room opera-5 weeks l tions (including h 1 General operating X X VEGP/ simulator) 4 16 characteristics Specific operating X X i characteristics Load changes X .X operating limita-X X tions ( Standard, emergency, X X i and plant pro-ceduras Control manipulation X Transients X VECP license and )( A technical specifi-cations License conditions and limitations Design limitations .e iO I I l

4 VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 3 OF 3) Minimum Description Typ.e Integral Duration Mitigating core Classroom or 1 day damage self-study Incore instrumen-tation Excore instrumen-tation 4 Vital instrumen-tation Primary chemistry Radiation monitor-ing _ Gas generation 3 [Observationtraining f including walkthrough Prior to VEGP VEGP 3 weeks achieving 20% power <a i 1 After V.EGP VEGP 3 months 10 eb. achieves 20% power Review and audit I week Obse.rvdion Munin Ihclnolin 0 * *" ' an 4u/allLlbe a%,

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I.n-P/s.d e edenea <o fo wee.):.s s eeIJ,. j n ws ,.,g, 2 (Prio" 4 W6P &*;egj$ pq f0M) a. [? ppli c a.. e .;.c ha.m g a ivuu, L::r Juulucc ".:gulate.f Cs.miccica licensed er ceet-ifico wait completa 3 weeks of " COP 4 -21kthr:u;h t ining. Applicants who have previo M y held an SRO license will no-b. be required to complete the 3 months of observation training. 10 They will completo 3 weeks VEGP walkthrough training instead. i 0*lk lic, test. lituh5 W'll also bAR Six(4) we.tkt b Amend. A. 4 2/84 "Y No*f i*" (ertucL As e d /i f '*8 qener/c Mtb /g, f d' Amend. 10 9/84 end. 16 4/85

E VEGP-FSAR-13 i l TABLE 13.2.1-2 (SHEET 1 OF 3) i LICENSED 3ENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH OTHER THAN PWR LICENSE OR NRC CERTIFICATION (ANY SUPERVISOR OR STAFF POSITION) s Minimum Deggription Type Integral Duration l10 Naclear power plant Classroom or 1 week i N theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards i Heat transfer, fluid J flow, and thermody-namics Fluids and matter Fluid statics 16 ) Fluid dynamics Heat transfer by 4 c o ndu c t ie r., convection, and radiation Change of phase boiling Burnout and tiow instability Reactor heat transfer 11mitu VEGF systems Classtoom or 4 seeks 10 Procedures for self-study desigr,and operating changes Pear. tor coolant system mechanical decijn i Peactt, ty :ontrot mechanisms and ine!1c a t ions ( Amend. 4 2/84 Amend. 7 5/84 Amend. 10 9/84 Amend. 16 4/85

'7 i VEGP-ESAP-13 TABLE 13.2.1-2 (SHEET 2 OF 3) Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve systems containment and shielding g((51-Radiation monitoring "IAl56.A7 system Auxiliary _ system _Radpactivewaste _ VECP license and Classroom or 1 week technical specifi-self-study cations License conditions and limitations Design limitations 4 16 19 i Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator ) Control room opera-5 weeks tions (including 100 h General operating X X VECP/ simulator) characteristics Specific operating X X characteristics Load changes X X operating limita-X X j tions / Standard, emergency, X X / and plant pro-ceduras Control manipulation X Transients X i Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85

I t /c AIlU4Q4hESII [3.1. / ML \\ Fuel handling and ' core alterations Facilities and procedures Classroom Control room opera-Simulator ~~~ ~~ 5 weeks tions 10 0 I (includinga h I Ceneral operating X X VEGP/ simulator) 4 16 characteristics Specific operating X X characteristics Load changes X X Operating limita-X X tions ( Standard, emergency, X X i and plant pro-ceduras Control manipulation X Transients X VECP license and technical specifi- )( E cations License conditions and limitations Design limitations I i 3 I

19 VEGP-FSAR-13 TABLE 13.2.1-2 (SHEET 3 OF 3) Minimum Descriptio_n Type Integral Durati_o_n Mitigating core Classroom or 1 day damage sel f-s tudy Incore instrumen-0 tation Excore instrumen-tation l Vital instrumen-tation l Primary chemistry Radiation monitor-ing Gas generation g obser/ation training' VEGP 3 months including walkthrough

• raining 7

Review and audit I week 16 19 Observa.lish %nly 3 me,,}f, a,Jdn alkBroyL (Alhe,v&GP acho'u A07* power) In lad e"fedenes U> 'ny wa.lkWoyh G weekt inci (f%er le Vr.4P adteny'

m. p.-a)

I' P r EEr~"E 'fD;' 5h i.... ; 2 0 p e : - -n v vv c r, 'rnlican*' M l4 a.g ce H 1. -: c n : c ; :ha n Lo s 0.ic a;.m vi nou m t + ~ r -

• t '" - v;: r ; e r c -

n3 Juinud af C e ne ri c f_e t t e r O '. 15 at t

• ra ri""t

~a j &L a t ; o.., appi:.; ant:-util have av Acan u - ~ ; P M UFnP e h i tt u pcricacc whi:P i nc htdr e u 1h th rowd. ^.r n a i ~;, Amend. 4 2/04 COIL Ikrsse als will have say

• s

^ mend. to 9/e4 ',,f;. Amend. 16 4/es ""' ?' "'d "' d' gin Genoic Ldkr 8Hg. A6ny. . _...,. _. ~ _. ..,. _. - _. ~.. _. _. _ _ - -. -.. _ _, __.___ _.____.__.____ _ -._,_ __..,___ -.-_ _,_.,_._. _ _ _ _ _ _, _ _ _ - _ _, _ _ _..

2D VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH 1 YEAR OF MILITARY PWR EXPERIENCE AS A REACTOR OPERATOR, ENGINEERING WATCH SUPERVISOR, OR ENGINEERING WATCH OFFICER (ANY SUPERVISOR OR STAFF POSITION) Minimum Description Type Integral Duration Nuclear power plant Classroom or 1 dI eeks l7 theory self-study Fundamentals of reacter theory General core design Radiological safety and radiation hazards Heat transfer, fluid 10 flow, and thermody-namics Fluids and matter 4 1 Fluid statics Fluid dynamics Heat transfer by conduction, convention, and radiation Change of phase - boiling ~ ~ ~ Burnout and flow instability Reactor heat transfer limits VEGP systems Classroom or 4 weeks 7 self-study Procedures for design and operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications Amend. 4 2/84 Amend. 7 5/84 Amend. 10 9/04 Amend. 16 4/85

1-/ VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 2 OF 3) Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve systems ATTNCN M g-lg,2,,[-3 Containment *and shielding Radiation monitoring g[MS6dT system Auxiliary systems pg[gyg-Radioactive wast ^~ l VECP license and Classroom or 1 week technical specifi-self-study cations I License conditions l I and limitations l Design limitations 4 1 Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator Contrci room opera-5 weeks tions (including 100 h General operating X X VEGP/ simulator) characteristics Specific operating X X characteristics Load changes X X operating limita-X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X Transients X Mitigating core Classroom or 1 day damage self-study Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85

et 1 ATTACHMEAT Tt3 Lt g 1 Fuel handling and w ' core alterations Facilities and procedures 108 ~ ~ Classroom Simulator Control room opera-5, weeks l tions (including # h 3 General operating X X VEGP/ simulator) 4 16 characteristics Specific operating X X characteristics Load changes X X Operating limita-X X tions ( Standard, emergency, X X i and plant pro-ceduras Control manipulation X Transients X VEGP licarse and )( A technical specifi. cations _ License conditions

• and limitations Design limitations

\\. .I i t f t

O VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 3 OF 3 ) Minimum Description Typ_e Integral Duration Incore instrumen-tation Excore instrumen-tation Vital instrumen-4 tation Primary chemistry Radiation monitor-ing Gas generation A Observation training VEGP 3 months including walkthrough training 10 1 Review and audit I week 06seron};bn -Indni le b M*Eb7 l'ncluding wnlkN ( ANw VEGP atWeves 20% fewer) h [ask e Itnce. W b wet /cf (neldh ref Wa (Ober* To llEGP achitV[ny } N o f Wtr aQ f rier

• n VFGP arkd : tin; 20 p;rcentPwer, app i 4 e n n *- e for cold 4 jiconene eke 11 wene 6 feeke er une p3rticip; tic,,;gerienen

,e . oomm mygo plac. i defi"rd h-j "--a r i Lm iic ; " ". 10 o i. m M i t 4 ^ -., applivo.w Jill '.e.; t ica. 6 weex:5 v f '.'ECP .12121. 10 I cn. p c r i c..c o whid 4nc1"da-talkthreu;h training, OY lo'ctMt. Jfll will hage gjy(g)witkS of bd [ g, 4 2,94 tyGFItnCf-as edltMd in,Gtaeric LeNer gy,jg y s^- _' Amend. 10 9/84 i // p...'. f.-f . Am. e n, d. 16 4/85 L... .,--..t. w.. ,. ~,, rs _-___w-,,,. - -, _ y-..,..,e__,.p..,.g. ,..w- ,m.. -.w.-- ,..,,,,g,,._

i LY j l VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH DEGREE IN ENGINEERING OR APPLICABLE SCIENCES (ANY SUPERVISOR OR STAFF POSITION) Minimum Description Type Integral Duration 3 m Nuclear power plant Classroom or h weeks l7 theory self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards Heat transfer, fluid 10 flow, and thermody-namics Fluids and matter Fluid statics 4 1 i Fluid dynamics Heat transfer by conduction, convection, and radiation Change of phase - boiling Burnout and flow instability Reactor heat transfer limits VEGP systems Classroom or 4 weeks l self-study l7 Procedures for design and operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications Amend. 4 2/84 Amend. 7 5/84 Amend. 10 9/84 Amend. 16 4/85

1f I 1 VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 2 OF 3) Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve g,2.FY systems g Containment and [6g '4 g7A shielding Radiation monitoring system Auxiliary systems 3bUbb0lE Radioactive waste dd A VEGP license and Classroom or 1 week technical specifi-self-study cations License conditions and limitations Design limitations Fuel-handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator Control room opera-5 weeks tions (including 100 h General operating X X VEGP/ simulator) I characteristics Specific operating X X characteristies Load changes X X Operating limita-X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X Transients X Mitigating core Classroom or 1 day damage self-study g Incore instrumen-tation Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85

i 7-4 i ATTAcMiE#F T 13.1./-y \\ i l } i. Fuel handling and core alterations j Facilities and - ~ procedures I l i l Control room opera- ~~ Simulator goo Classroom l ~~ " ' ' " ~ 5 (includinga[h weeks tions 4 16 1 General operating X X VEGP/ simulator) 8 ' characteristics Specific operating X X characteristics Load changes X .X operating limita-X X tions ( Standard, emergency, X X 1 and plant pro-l ceduras Control manipulation X Transients X l VECP license and Q g technical specifi-cations License conditions and limitations Design limitations i i. h A

i 2-7 VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 3 OF 3 ) Minimum Description Type Integral Duration Excore instrumen-tation Vital instrumen-tation 4 Primary chemistry Radiation monitor-ing Gas generation Observation training *** VEGP 3 months including walkthrough 10 training Review and audit 1 week lf obsendk %i 3 3 mo Hs undudig walk %f ( ANer veGP act,ieues 2.07, 7ower) 5h-fa.nh jonce b ween lMc$uYfn b I, (UK h$0V VEG f d.citteVin 2.0f, f**] _.__'.,_._,'_,,,,',.4, l4 a h, 2 ^^ ~ ~ - + - ma a -

_t_,

,, _, u ___m m ,---__4-rm+ __ oo ,e _m =^^*^- --^'~ --.......aa.,u ^* """" 10 Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85

tr A77Acafe>/r A _ I'hrsu /h,$r ukll base stX(4) cuecks of bib KJ Ibn 25 ertext Q2 0 h $1 &catric 8Y~lC, l-1

• // L,rp

^'

t. e

..f f/w r> ./L .. ~ < ~ wi. ",'^L"'", ~' x . (- s, .. ~ ~ wmuy t riu nsr w LA/UF~ 'm -1 t I i 1 l I I t I. i k .I a l e I hii

i L4 VEOP-ESAR-13 TABLE 13.2.1-5 (SHEET 1 OF 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS-PERSONNEL WITH HIGH SCHOOL DIPLOMA OR EQUIVALENT (ANY SUPERVISOR OR STAFF POSITION) [ e s c r l _o t i on I222 Integral Duration Nuctear power plant Classroom or 12 weeks theory self-etudy 10 Mathematics Fundamentals of reactor theory General core design Peactor and health physics and radio-logical safety Materials Heat transfer, fluid flow, and thermodynamics Fluids and matter 5 4 Fluid statics Fluid dynamics 16 19 Heat transfer by ccnduction, convention, and radiation Change of phase - boiling Burnout and flow instabliity Reactor heat transfer limits VEGE systems Classrcom or 6' weeks 10 self-study Procedures for design and ope rating char.ges Rpactor coolant system mechanical design Reactivity control mechanisms and indications c Amend. 4 2/84 Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85

Jo VEGP-FSAR-13 TABLE 13.2.1-5 (SHEET 2 OF 3) Minimun Descriction Type Integral Duration Reactor safety g T 13 A'j[ systems Emergency and reserve EII gAC systems Containment and shielding Radiation monitoring ME' system Auxiliary systems Radioactive wast A-p VEGP license and Classroom or 1 week technical specifi-self-study cations License conditions and limitations Design limitations Fuel handling and Classroom or - 3 days 79 core alterations self-study 4 16 Facilities and procedures l Classroom Simulator Control room opera-5 weeks tions (including 100 General operating X X VECP/ simulator) characteristics Specific operating X X characteristies Load changes X X Operating limita-X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X Transients X f Mitigating core Classroom or 1 day damage self-study ,Incore instrumen-j tation Amend. 4 2/84 Amend. 16 4/85 Amend. 19 9/85

i l' ATTAcRNedT T 13 2.1-T i Fuel handling and ' core alterations-Facilities and procedures ~ Classroom - ~ " ~ ~ ' ' ~ 5 weeks l Control room opera-Simulator tions (including 100 h 4 16 I General operating X X VEGP/ simulator) ' characteristics Specific operating X X characteristics Load changes X .X Operating limita-X X tions ( Standard, emergency, X X 1 and plant pro-ceduras Control manipulation X Transients X VEGP license and )( g technical specifi-cations. License conditions and limitations Design limitations-t I. 8 i I h 6 l 5 ,,.v., --w.- y

32 VEGP-ESAR-13 TABLE 13.2.1-5 (SHEET 3 ai 3) Minimun Description Type Integral Duration Excore instrumen-tation Vital instrumen-10 tation Primary chemistry Radiation monitor-ing Gas generation ! Observation t r a i n i ng 3 ' VEGP 3 months including walkthrough training Review and audit I week Str\\fJionpaininy 3 ag 16 1 Wle* g unIk}broyl, Includi ~ VW achieves 207, f*) 1 In-glad erferience imkliy <a> Geseek w/kAg4 (fee to VEGF acGeviny 2.0% (*"] l4 P: ;- te ~/ : C ~5 a"i.; 20 pe rc e rrt e : c r, :ppi..oute f+c ,- a_ s -wei t w2v. c .;cg3 u; n ;t g 3r-i

p;;i;;- _vnerionr#

2r if....l':y Cc eric Lett_. os-lo at : ; ;.-.. w.,_12nt I -- eddi* inn ';;1 ; c a;.t - will L-m R om. 0 mma f '15"" chift-to p;cr._c:: h i -k in 1udar ::i-k en rsuch t-r z i n i-ng. e AmcHQ A Amend. 4 2/84 l Amend. 10 9/84 Amend. 16 4/85 Amend. 19 9/85 l

I 33 l ) 477AC#MEAlf k i ICtp$g f3 g( $/ ) Qth 0 0 ar&yan op*!! a o&ed as Gewie 8HG. % enexe / ,,r_ ,.. // ) n, L.e .2 uca P -! l _ ; ypuu ms r ws.. - - (- Lil l l_. f. JI i 1 y l w c,.-- s. m-vi a ~ <<i l t t l I e l I! I h. e I t i i i 11

f 34 VEGP-FSAR-13 j 4 TABLE 13. 2.1-6 ( SHEET 1 OF 3 ) L~ CENSED OPERATOR ONSITE TRAINING SYLLABUS (PLANT OPERATOR OR ASSISTANT PLANT OPERATOR) Minimum Description Tyge Integral Duration Nuclear power plant Classroom er 12 weeks theory self-study Mathematics Fundamentals of reactor theory General core design Reactor and health physics and radio-logical safety Materials Heat transfer, fluid flow, and thermodynamics Fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convention, and radiation Change of phase - boiling Burnout and flow instability Reactor heat transfer limits VECP systems for Classroom or 12 weeks electrical and self-study reactor control Reactor coolant system mechani-cal design Reactivity control mechanisms and Indicators Reactor safety systems ( Amend. 19 9/85

VECP-FSAR-13 TABLE 13.2.1-6 (SHEET 2 0F 3) Minimum Description Type Integral Duration Emergency and reserve systems Containment shielding Radiation monitoring systems Auxiliary systems Classroom Simulator Control room 6 weeks operations (including 100 h General operating X X VEGP/ simulator) characteristics Load changes X X Operating limita-X X tions St,andard, emergency, X X and plant pro-cedures-Control manipu-X lation Transients X Mitigating core Classroom or 1 day damage self-stud,y Incore instrumen-tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation moni-toring Gas generation s Amend. 19 9/85

VEGP-FSAR-13 TABLE 13. 2.1-6 ( SHEET 3 0F.1) Minimum Description Type Integral Duration A Observation training'** VEGP 3 months including walkthrough training _ Review and audit I week ChSEPVa[l061 NM[n 3 Mon f ihcidh wa.lkNr k (AHer v4P diever 27 P'"'c') n_ ed eytea-c,,,3 e in d in walkhronyk (frib r Nf RC.NtVinJ e 20 7, yower) . #. m "eco - 17.; :c pr---- ~..,

is

n r < e.-

"MA liae" rc ill v..yl;te eb: r ;; tier trair.ir.g ;;. e per-ble 1.;c.. sed en==- ei:1..uulo.r pcuer p1=r*_ fer : p; mu sf 0 : -km .Ln.-add *2 i nn. anplic r.ts _ill '. 'f: at 1;; t S mmio or "eco k4 rb expenence which in:lude;.clhthisy. L.ainir~ ruses.T ATTACHNUT A 0366V Amend. 19 9/85

_g 37 ATTACRMEAT b j a k any espenexe o oJAhed in Gewie 8'f-16.6, l i 9 f I ) e i i a t t i 4 1

3f GdNERAL MANAGER MANAGEn NUCLEAR TRAINtNG i I SUPERINTENDENT NUCLEAR TRAINING SB0 ORAFTSMAN CLERK I I SUPERvlSOR SIMULATOR OPERATIONS MOO #FICATION TRAINING SUPERVISOR SAO I I i j SIMULATOR . SIMULATOR PLANT INSTRUMENT' ENGINEER INSTRUCTOR ENGINEER TECHNICIAN SAO Sno [ l I i SUPERVISOR - SUPERVISOR PLANT MPICHEMISTRY T R AINING TRAINING I I I I I I METMOOS AND SENIOR METHOOS METHOOS ANO SENIOR METMOOS TRAINING ANO TRAINING TRAINING ANO TRAIN 4NG SPECIALIST

• SPECIALIST SPECI ALIST
• SPECIALIST LEGENO.

SRO + Senior reactor operator licensed or Certified.

• Methode end training Specachets well have espenence en electrical or mechnetel maintenenCo. enstrumenteteen and controse technology. or heetth physics and chomestry.

( Arrend. 16 4/85 voGrLE VEGP TRAINING OPGANIZATION GeoreiaPower

• cEcmc GENE 44mm ANr O

UNIT 1 AND UNIT 2 FIGUPE 13.2.1-1 1AnCM

1 (m .~. ,i l SUL He4 j JAN 81 JUL 84 JAN 85 APRile-M 86 SRO = senior reactor TO TO wTO ot TO gTO ope,,,o, JUN 84 DEC 84 38Mk86 86 M 86 RO reactor operator = initial Classroom NLO = nonhcensd Training SRO 18

n RO 18 3

r-Operator ]

• g

{ (Fundamentals, Systems) F NLO 18 g RO*9 y j { st&u expectd to Simulator SRO 18 RO9 = a -

2 complete future training.

E

• • Su o t

tors Hot Participation SRO 10 SRO*4 SRO 4 RO 6 (Extra Man on Shif t) RO 12 _ g g RO4 E RO'14 9 9E 2 Unit 1 fuel load. Review and Audit SRO 18 NLO 18 x g @x 5 1 SRO'9 1" SRO*9 K NRC License Exam RO*9 RO'9 ~ i l J i Technical Specification Minimum Staffing i (g?_ :_y Unit Operation y-Unit Operation s j Available Personnel ..._.-. Staffing for 6 Shifts) Staffing for 6 Shifts), J Senior reactor operator ] (including shift technical 18 18 18 adnsors) I Reactor operators 12 18 18 Nonlicensad operators 12 18 18 i Amend. 16 4/85 VEGP UNITS 1 AND 2 VoGTLE ELECTRIC GENERATING PLANT ~ OPERATIONAL TRAINING Georg. Ibwer i ia unir i nno unit 2 PIGUPE 13.2.1-2 Y an.

r. i l I l l t MONTHS TO FUEL LOAD 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 i Preoperational License Fuel Load j Tests Exams and Unit 2" Criticality 1 o l 1 l Licensed Operators (12S) (6M) to Support Preoperational Tests i i. j Nonlicensed Operators ,j to Support Preoperational Tests ( S* *) (6M) j i l Licensed Supervisors (7S) (6M) to Support Fuel Load 4 1 l Licensed Operators j to Support Fuel Load (12S) (6M) l 1 Legend i M = Minimum staffing plans 4 i S = Students who start training For the operation of Unit 2, GPC expects to license a minimum of 18 addet6onal individuals. Licensed individuals will have a dual license for both Units 1 and 2. i ) Depends upon turnover. ADDITIONAL VEGP UNIT 2 1 VOGTLE ELECTRIC GENERATING PLANT OPERATIONS TRAINING t Geoigialhvci-u T i Ano on T FIGUPE 13.2.1-3 i sne b i \\

s-g 10SE M p ACS $ dT I3* 41 i VEGP-FSAR-13 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. AFPersonnel 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. g,yMLHT 13.2 13.2.2.1 Training Program 745EE7 ~~~ A training program has been established for each VEGP organizational group.AfAt the time of fuel Tbau, 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. Significant amounts of nonlicensed personnel l' training were accomplished prior to the start of preoperational (tests.,g- ~ 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 same 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. A previous course of instruction has been completed which e 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 topics may be taught and course completion may be granted. i l 13.2.2-1 Amend.16 4/85

~- V2 dTTAt#HEWT /3 2.2._ fersornne./ will meeb lbe whdnum cdacabon and 'enee regiremeds of AysZ It./-197/ cons guAid b erkrm aH ksks?rhe h feh,ihd 9 aJ/yAMst 17./-l37/ 3,ameds, perso,,, meef le. Indned foker/o'm yeciAb fske <nd gu.aA id edeoIfly. jeAv,a-Le sks y l 3 I j' i i l' i 'i j l s

n i l ATTAc##Edr /3.1.2./ af ersonnel indidd th TaWe /3.2.2.-/ Ti e-nauriber.s ? t l wi// fue awed L hash added a A M/e ik com,d f e d i. 5 //0w h y u. J ' order k sy,fv' preyeda f y o load and h,; cdiea.Wy, efuen,ed,oas.al wyt \\ ,nendf coyefe aWa/ fwh - one yea of a.ssgnmed 1' $4enguico,,ds pnyawa Lelove. and a.)hr /ud /posW o d willie Be an?e l exey as nded in aa%a/ yvyrai, desajiks. i 1 5 l-i

"7 s u. z.u. VEGP-ESAR-13 Completion of an examination by the trainee which is e 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 programs for the following organizational groups have been established: Mealth physics /r:dic:'- " ~ a 13.2.2.1.1 I strumentation and controls 13.2.2.1.. 3 Mechanical maintenance 13.2.2.1. Y Electrical maintenance 13.2.2.1.% 5 Shift technical adv: :sor 13.2.2.1.% (, Nonlicensed operator 13.2.2.1.% 7 Licensed operator 13.2.1 Training (instructo: qualification) 13.2.2.1.5 8 General employee tr..ning 13.2.2.1.h 9 Eire team training 13.2'2.1.5 10 Quality control 13.2.2.1. N 11 Engineering and tec'thical support 13.2.2.1. R p. The syllabus for each truining program, including the duration and the organizational group receiving the training, is described in the following, subsection or paragraphs. Traininy %)wn 13.2.2.1.1 HealthPhysicsgadiochemistryTrainingProgram, A. Initial training -fe^<An :c.ien Technicians will meet the minimum education and experience I requirements of ANSI 18.1-1971 prior to being considered qualified to y perform all tasks independently. Prior to meeting all ANSI 18.1-1971 requirements, technicians may be trained to perform specific tasks and qualified to perform those tasks independently. Technicians vill be required to complete general employee training per the requirements of section 13.2.2.1.%. 't The numbers of technicians indicated in Table 13.2.2-1 vill have completed the training indicated in the Table in ordar to support preoperational testing. Following fuel load and initial criticality, replacenent technicians will normally complete initial training requirements within one year of assignment to the position. Initial training shall consist of pressurized water and balance of plant systems, nuclear physics fundamentals, radi.ation protection, mitigating core damage and on-the-job training. The initial program vill have a minimum duration of 6 weeks. On-the-job training prior to fuel load and initial criticality, shall be comprised of participation in preoperational program activities, procedure review and preparation. After fuel load and initial criticality, on-the-job training shall be comprised of activities which build upon the initial classroom training. ,~c=----l85 t i. " ",. -n!cv i n 1. A.*k.

YV 4 l VEGP-FSAR-13 ^ ~ N Approximate Curriculum Outline Duration General employee badge and health 6-10 h physics training Industrial safety 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week f Nuclear physics fundamentals 2 weeks Radiation protection 1 week Chemistry fundamentals 1 week Mitigating core damage (commensurate 2h 4 with responsibilities) On-the-job training 1 week ecencipi B. Continuing Training One of the following listed programs or other specific programs as requested by the health physics ndggw I superintendent will be conducted annually. He r a c.-. : 1-who have not completed the offered course will normally 1 attend. Approximate Curriculum Outline Duration Advanced health physics I week fAnalytical chemistry 1 week Radiochemistry 1 week LCorrosion 6 G Amma. Spetirosupy I week. C. Annual Requalificaffon Training or Exemption Testing >s' Health physics [cbemistry> 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 j protection, security, and respirator procedures. Initial Foreman Qualifications ([and Student Engineers'T]) D. ,.- ~ f Foremen who meet the requirements of ANSI /ANS 18.1-19e will complete General Employee Training and on-the-job (training as a. r n de epd ether the individual attends additional da pr as described in paragraph _ing fr- .8. Nteisll M4Q n emuds-of AUS$ If,l-197f. N 7[$1 D \\ m k ? T L s,( 1 4 d % e 2, 2 g k m..d y s. P e s uv era w

C odors wih edurlin and e triesct Oo.t Mtt.fs cr e.teet)s rsAR. eenmke,h ma \\\\ r ps; im readel L+ # s uideele t ean,y (;yg & ;,, ;ggg.,, jg.,e HedH, F% pies q \\ n e me.t$s or tXcet ,,,) g, $bt refuiremedt for *ff t. pos'fjory, S g VEGP-FSAR-13 / [describedaboveunderinitial training prior to performing independent duties. 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 7 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. Foremenwilll7 normally attend these continuing training sessions l unless they have already completed the offered course. f F. Health Physics {ChemistryJ Supervisor Qualifications and Training The health physicsfchemistrvlsupervisors will have the qualifications required of health physics (/ chemistry foremen and will normally attend a similar continuing training program. f.oodry=herS G. . c r -_ " ~ = d ::c. E7 mp m 1 A-fPersonnelwithexperience cnat exceeds Nuclear f 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 y is. z.1. /.2. Q#SEET ATTACHHDIT /3,2.2. 6 O IS.L.1. l.3 a.usEtr ATTwMeut 13.11./.3) i A. Initial Trainina , Technicians who miet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training and on-the-job training as described t below prior to being assigned independent tasks. Those ] who do not meet the above requirements must complete f initial training in order to demonstrate their ability o perform the specific tasks. N j Amend. 7 5/84 13.2.2-4 Amend. 16 4/85

li ATTAc-HHEUT I3.2. 2..t. 2.

• s Ik 4

k._ l i i p . _ ;;..~.,:.. V 13.2.2.1.2 Chemistry training program I i A. Initial training g TecAn " ^i Technicians wil'aun l meet the minimum education and experience i '1 requirements of ANSI 18.1-1971 l perform all tasks independently. prior to being considered qualified to Prior to meeting all ANSI 18.1-1971 requirements, techniciana may be trained to perform specific taska and i qualified to perform those tasks independently. Technicians will be required to complete general employee training per the requirements of section 13.2.2.1.k. 1 ~ The numbers of technicians indicated in Table 13.2.2-1 will have completed the training indicated in' the Table in ~ order ~ ~to support ~ ~ 1 preoperational testing. replacement technicians will normally complete initial trainingF ..g ] requirements within one year of assignment to the position. training shall consist of pressurized water and balance of plant Initial i systems, nuclear physics fundamentals, chemistry fundamentals, mitigating core damage and on-the-job training. i The initial program will have a minimum duration of 6 weeks. On-the-job training prior to fuel load and initial criticality, shall ~Wroceduredeview-aiid Yre"perahtons. Af ter fuel load a .i a criticality, on-the-job training shall be comprised of activities which build upon the initial classroom training. l i ,h & $Y l One of the following listed programs or.other specific programs as requested by the h::ith +hysicsc chemMfrg. t superintendent will be conducted annually. ---"~" who have not completed the offered course will no Personnef attend. rmally l l Curriculum Outline Approximate Duration i Ad. ICQf

• ld5h.f._ -

'G Ch*K ...~ C-f - - ). = N..@.235. Ur.. ~ 1 ..~.~-__,____-_,m. ._mm,._,,__,y,,,r-,_.,_., ,,_r.___..r,..,,

l: hTTACHMEAIT /3.2.2.l.2. 4<. il C. Annual Requalification Training or Exemption Testing k T.s el ti. emistrKtechnicians will complete annual requalification training or exemption testing l to make them aware of and review important changes i made to plant emergency and disaster, j radiation protection, security, and respirator procedures. D. InitialForemanQualificaEions Foresen vill meet the requirements of ANSI 18.1-1971. General employeetgainingvillbecompletedpertherequirementsofsection i 13.2.2.1.A. Foremen vill complete training in mitigating core damage. } Any other training maybe requested by the chemistry department; i S p ;wte,utent. l i E. Continuing Foremen Training i i l One of the listed continuing training programs or other ' s specific programs as requested by the i.eelth-physicst. ch'emis7r4 ~ superintendent will be presented annually. Foremen will 8 normally attend these continuing training sessions-unless they have already completed the offered course. t 4 ._ V F. Ith-Physic hemistry' Supervisor Qualifications and .l raining W The kl-th-physics 1hemistry supervisors ill have the qualifications reqtiired of:nce: m-envam _hemistry foremen and will normally, attend a similar continuing ] training program. ver - - - i s C. Contractors --~ 1 Contractors with education and experience that meets or exceeds I FSAR comanitsents may fill a position provided that the{ _M 7,;;;Q CEtMih Superintendent certifies that the individual's education and J experience meets or exceeds the requirements for the position. I I f 1 z._ p ~ ~.m-5 ~.. - i 6 i ... - ~

ATTACHNEv7 /3.f..f.,/.3 D _9_ r. lI. 7 13.2.2.1.3fnstrumentation and Centrols rograa A. Initial training y techn i Technicians wi d* % meet the minimum education and experience L l requirements of ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all ANSI 13.1-1971 requirements, technicians may be trained to perform specific tasks and i qualified to perform those tasks independently. Technicians will be i ~ required to complete general employee training per tihe requirements of ~ section 13.2.2.1.. 1 8 The numbers of technicians indicated in Table 13.2.2-1 vill have I completed the training indicated in the Table in order to support. preoperational testing $ will normally complete initial trainingFollo replacement technicia i requirements within one year of assignment to the position. Initial 1 training shall consist of pressurised water and balance of plant systems, process fundamentals, mitigating core damage and on-the-job training. The initial program will have a minimum duration of 5 4 weeks. On-the-job training prior to fuel load and initial criticality, shall )*:s*STdMIMhigtfon in Preoperational program activities, ' t. /, Af ter fuel load and initial criticality, on-the-job training shall be comprised of activities j vliich build upon the initial classroom training. l 4 . e,. -11 < :. - ~ - t B. Continuing Training ~~ ~ ~ ~...- N-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. '.' ?.. 1" .., ;.- 1 Approximate Curriculum outline Duration i Electronics review l ~ 1 week l l Test equipment 2 days i Process instrumentation I week Process control systems 1 week ~ t j j C. Annual Requalification Training or Exemption Testing l j Instrumentation and controls technicians will complete i annual requalification training or exemption testing l to make them aware of and review important changes made to plant emergency and disaster, radiation ~~~ ~

• protection, security, and respirator procedures, i

l .t 1 -i- ,.,,---.+.,--v-,--y-.-w a .,-,w.v----.,-------,v.--~-,- .---m,-,vnrv.ww,+.,,,-.- .w---,w,%..,-,.,-..v.--e.3--,,-v,-..y-.--,,-%.-e-v.--

4 I i df 6i ) l i 1 I D. Initial Foreman Qualifications Foremen will meet the requirements of ANSI 18.1-1971. General j employee training will be completed per the requirements of section 13.2.2.1.ff Forenen will complete training in sitigating core damage. Any other training maybe requested by the maintenance department. s-r.- ..v u. u ~ ~*' ~~ ~~ E. Continuing Foremen Training j e.- One of the listed continuing training programs or other Z' spec'ific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend these sessions unless they have already g M completed the offered course. '~ F. Instrumentation and Controls Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the i j qualifications required of maintenance foremen and ~ l will normally attend a similar continuing training pr.ogram,_ Af ter i_.ni_tiatl.__appnintment..to_ that_p.osition,. the new supervisor will complete the following training. I Approximate l ~ Curriculum Outline Duration -r -Electrical, pressure vessel, and ' 3 days ~ piping codes and standards l (including nondestructive testing i d c-review) 0.L

• C. ~ Contractors

. *; 3.. * * :...; l ~ ~'

• l Contractors with education and experience that meets or exceeds FSAR couaitaants may fill a position provided that the Maintenance 2<

Superintendent certifies that the ladividual's education and experience meets or exceeds the requirements for the position. i 1 f } i 4 4 l! I

99 VEGP-FSAR-13 Approximate Curriculum Outline Duration General employee badge and health 6-10 h physics training Industrial safety 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 l with responsibilities) l4 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 I Curriculum Outline Duration Electronics review I 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 j 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 General Employee Training Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph 13.2.2.1.8.A. Amend. 4 2/84 13.2.2-5 Amend. 16 4/85

DELETE VEGP-ESAR-13 f and on-the-job training as described above under initial training prior to performing independent duties. 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 f superintendent will be presented annually. Foremen will f 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 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 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 departmer.t may also accept prior training or experience to fill specific course requirements. i t l 13.2.2-6 Amend. 16 4/85

$b g l3-g6 psen } VECP-FSAR-13 \\ 13.2.2.1./,/MechanicalMaintenanceTrainingProgram A. Initial Training Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training and on-the-job training as described below prior to being assigned independent tasks. 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 6-10 h<a Industrial safety 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Maintenance fundamentals 1 week 1 Mechanical fundamentals 1 week On-the-job training 1 week Continuingg} Training ~ d\\c. B. One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually.g r -- -- ' who have not completed the offered course ill normally attend. Ne.clicude,s 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 Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph l 13.2.2.1.8.A. 13.2.2-7 Amend. 16 4/85

i i ATTAC.HMEllT 13 21/ Y si f l

i 13.2.2.1.4 Mechanical Maintenance Training Program j

rnfcham c. ii A. Initial training mecNaoGC5 Maintenance ;;x;... 4v111 meet the minimum education and experience 8F requirements of ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all AKSI 18.1-1971 3: requirements, ; x - ' may be trained to perform specific tasks and qualified to performOhose tasks independently. h vill be required to comple e general employee training per the requirements of section13.2.2.1/ g The numbers of personnel, indicated in Table 13.2.2-1 vill have completed the training indicated in the Table in order to support i. preoperational testing. Following fuel load and initial criticality, l} replacement puc,....el' vill normally complete initial training M requirements withinIone year of assignment to the position. Initial .a training shall consdst of pressurized water and balance of plant systems, maintenaned fundamentals, mechanical fundamentals, and i, .o on-the-j ob trainin '. The initial program vill have a minimum duration of 5 weeks. th dutsiC 5 ,I I' On-the-job training prior to fuel load and initial criticality, shall I'y M "g Q Q M gigi g % preoperational program activities, P in

iJ 7 - nz-After fuel load and initial criticality, on-the-job training shall be comprised of activities J-which build upon the initial classroom training.

I i t I 1, II e I b ii ..,----.-.---,-----,,-,.-,.-e. ,..,,..-_-..,,-,,,,v,

Foremn wilI meel -fhe repiremes,( pag 7,_,_ g 13 Y '}, "'tn o ed 7; b)' Ne maidenact k p-FSAR-13 $tesQ 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 r.ade to plant emergency and disaster, radiation protection, security, and respirator procedu,res. g liAlsfi*n3 D. Initial Foremen rainingV(and Student Engineers) (Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete General Employee Training and on-the-job ftrainingasdescribedaboveunderinitial training prior to performing independent duties. 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 perfor, specifictasks[ e E. Continuing Foremen Training One of the listed continuing training programs or other l' specific programs as requested by the maintenance 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 vessels, and 3 days piping codes and standards (including nondestructive testing review) G. J.cuche * * "ci Emplay s Coedradorg Personnel with experience that exceeds NRC commitmen i may fill a position in the mechanical career path provided that the maintenance superintendent certifies Coedrwedo(s w;+b,,J,,,,f;,,, d u e,.;,,,ee. Sd de w md FCAR comml/f.,u'fs I that the employee's experience cualifications excee s " [*' b a '8bd. km d 16 4/85 4~ d cycim,,eaa nan.h s.e y<', gar n,,,,,y,,,, i

r, r

I_,,_

St VEGP-FSAR-13 /'~the position requirements. The training department 33%EET may also accept prior training or experience to fill l ATycpq specific course requirements.7 I3.1.2..I.c 13.2.2.lf/3 lectrical Maintenance Training Program .A.

initial, ng WTE Maintenance personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training and on-the-job training as described below prior to being assigned independent tasks.

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 6 - 10 h c a > f Industrial safety and first aid 4h I 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 I week 10 / test equipment On-the-job training 1 week B. Continuing Training l 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. Duration depends on whether the individual attends additional a. radiation worker training as described in paragraph 13.2.2.1.8.A. 7 Amend. 10 9/84 13.2.2-9 Amend. 16 4/85

$2 ATTAcHHEDT I3 2.2.l 5~ 13.2.2.1.5 Electrical Maintenance Training Program 6 .r. - l Initial ^ training A. g,lCc.fr7Ca*AAS EJ a c;f f *cie>t o j ?.n :enan:e'.e.w-+=ne vill :ee t the -unicum education and experience i e;.irare.:s Of.d"*

• 3. ' '. F '. p r i o r :: bein:; ::n.?idered ;uslified to perform all tasks independen ly.

I'rior to meeting all ASSI 18.1-1971 requirements,, ;;_..;1. may be trained to perform specific tasks and Athose tasks independently. ?,:: ---"[ vill beF/eg,,7 "d5 qualified to perform _ required to compiege general e=ployee training per he requirements of section 13.2.2.1.). ge$chician $ The numbers of ;n.,,....;1: indicated in Table 13.2.2-1 will have [Y,q_ogleped the training itylicated in the Table in order to support 7 plant (testing. Followingifuel load and initial criticality, 7 replace =ent p:x r f l:will normally complete initial training ?[ requirements within one year of assignment to the position. Initial training shall consist of pressurized water and balance of plant ~ systems, maintenance fundamentals, direct current fundamentals, alternating current fundamentals, electrical safety, drawings, test equipment and on-the-job training. The initial program will have a minimum duration of 8 weeks. f On-the-job training prior to fuel load and initial criticality, shall N2S"Ug-gapigi t on in preoperational program activities, be compris g r_ p -* *- , Af ter fuel load and initial criticalitb on-the-job training shall be compri sed of activities which build upon the initial classroom training. Continuing Training B. E"feclocan l One of the following listed programs or other specific programs as requested by the maintenance superintendent l will be conducted annually. n ....cl who have not completedtheofferedcoursewill(normallyattend. Electr;<.;nn s i ,A. i l-Approximate Curriculum Outline Duration i ~~ Protection devices, control devices, 3 days and motor control centers ac/dc motors and generators 4 days I Solid state theory 3 days L Batteries, chargers, and inverters 1 day ~ Pyrotronics fire detectors 1 day i Motor-operated valve maintenance 1 day Switchgear and breaker maintenance 3 days Amp lugging i day .g ~..... _. .I'.. ~ i i ,,+n- -,n

Forea,er, will meef *lke regirenerb ol AMI If./-197/. GQ emjdayee +ra'arkt will be comfefed er 4he 4ce 4 g f+ seifron 13.2.2.13. Facemu ill c4 fad b 4Ae. md@%_ *[A DI'*% h, f re y " " * *j

• 8 Approximate Curriculum Outline Duration Protec on devices, control devices, 3 days and.otor control centers ac/d motors and generators 4 days Sol' state theory 3 days Ba eries, chargers, and inverters 1 day Py otronics fire detectors 1 day M tor-operated valve maintenance 1 day witchgear and breaker maintenance 3 days Amp lugging 1 day j

C. Annuai equalification Training or Exemption Testing Electricians will complete annual requali fica tion 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 harEA Student Engineers)

1. coremen who meet the requirements of ANSI /ANS 18.1-1971 will complete general employee training and on-the-job training as described above under initial training prior.

to performing independent duties. Those who do not meet the above requirements must complete initial training i and progress through most of the continuing training in order to demonstrate their ability to perform courses 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 continuing training programs unless they have previously completed the offered Course. F. Maintenar.ce Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program. Af ter initial appointment to the position, the new supervisor will complete the following training. 13.2.2-10 Amend. 16 4/85

% & ors W 0$ & ion & u D w. Q Q,y 16 SI exceeds FSAL com,,ah,,en{s Hsinienne.Qmderde.<f ef,y.p,y f'N.f * ' N i h d f .g kG -FSAR-1$ 3 " N r OS/ e Approximate Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including g nondestructive testing review j

.pic'; 2-hYtMYets G., -1 :.:' :.h ;. t.,

uad M:2 ersonnel with expe2 ence that exceeds NRC commitme s 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 fil specific course requirements. 6 13. 2. 2.1.jir Shift Technical Advisor Training Program A. Education Requirements Shif t technical advisors will have a bachelor's degree in a scientific or engineering discipline. 16 B. Training Program The candidate holds or has held an NRC senior reactor operators license for that type of reactor, or the candidate completes a Georgia Power Company (GPC) shift technical advisor training program described in table 13.2.2-1. In either case, the shift technical advisor shall receive specific training in the response and analysis of the plant for transients and accidents. C. Experience 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, a D. Requalification Training for Shift Technical Advisors Shift technical advisors will attend the same requalification program as NRC-icensed operators. Shift technical advisors hich o not stand shift for a 4 l~ period of 30 days or longer will receive on-the-job instruction from the duty shift technical advisors 6~ior la Ll (Q STA's dll M tl $best f"*tE'by$*e"n. 6 4/85 gT Y *W4 g f*Inig af /cuf t' week.r d 4M .2. Amend. 17 7/85 lt '%e f pe.p a,n, y

VEGP-ESAR-13 concerning plant changes which have occured during their absences. .TM5ELT Persons not performing the shift technical advisor 4 4TTdW function for a period of 6 months or longer shall, prior d'lyI7 to assuming the responsibilities of the position, undergo an individual requalification program. 13. 2. 2.1.)if Nonlicensed Operator Training Program ggg 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. Approximate Curriculum Outline Duration General employee badge and health 6-10 heas 1 physics training Industrial safety 4h NeR employee fire training

2. h Nuclear power plant fundamentals 1 week Power plant components 1 week VEGP systems 4 weeks On-the-job training I wee d

B. Continuing Training g r After completing initial qualificatio p;n#j s the nonlicensed operator will complet x,g o th4 plant systemsaon which he3was not initially % n i #iM. Normally, the nonlicensed operator will be. balel qu;11f5 on all systems,outside the control room and containment during the individual's first 3 years in the plant operations departmen. [g h;3/herarca of respeQ;/ hg Annual Requalification Training or Exemption Testing Nonlicensed operators will complete annual requalification training or exemption testing to make ~ ,7 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 Amend. 16 4/85 13.2.2-12 Amend. 17 7/85

ATTACHM@T 13.2 1 l. 7 <s ^ l 13.2.2.1.7 Nonlicensed Operator Training Program A. Initial training Personnel vill meet the minimum education and experience requirements cf ANSI 18.1-1971 prior to being considered qualified to perform all tasks independently. Prior to meeting all ANSI 18.1-1971 requirements, personnel may be trained to perform specific tasks and Personnel vill be qualified to perform those tasks independently. required to complete general employee training per the requirements of section13.2.2.1.f.4 The numbers of personnel indicated in Table 13.2.2-1 will have completed the training indicated in the Table in order to support preoperational testing. Following fuel load and initial criticality, replacement personnel vill normally complete initial trainingInitial requirements within one year of assignment to the position. training shall consist of power plant fundamentals, power plant co=ponents, pressurized water and balance of plant systems, and on-the-job training. The initial program will have a m,inimum duration of 7 weeks. On-the-job training during preoperational and test program activities shall be comprised of equipment operation, equipment checks and system / component testing. Af ter fuel load and criticality, on-the-job training shall be comprised of activities which reinforce the initial ] classroom training. Co tiru ng raining' ~ k. Afte mple ng i'nitia q6alifica o n's, the l h,, rator wil complete alification el n whi he was no initially nonli ns he'p1 t\\syst onlicensed operator wil m_\\ ' f, d 'q alifi g Nor

lly, the con rol room and all s tems out ainme k durin the indi dua

_ fi t 3 years in the lify N Y.co pla oper ions d a rtmen't. (,p or Exempt on Testing Annua Requ ficati Trainin [' g Nonlic sed op ator's ill comp 1 te annual ion testi to make requali ' cation raini or exem i em aware f and r iew i. o~rtant ch ' ~~ P ant emerge cp, rada tion otecti n,

security, nd 1

re pirator p

cedures,

~~~-MCNon censed Ope ator Pro ressi Afte completingi license traini g progra many opera rs will pro ress to cense positio The b licens d training 3 ograms a desc ed in section.- 13.2.1. I 1 .,,.., - _ - -. _,,,. - - - ~, - - -.,. - - - -,,.,. _,.,. _,. _ - - - -. - - _ _ _. - _,.... -,. - - - _

VEGP-FSAR-13 1 them aware of and review important changes made to plant emergency, radiation protection, security, and respirator procedures. p Nonlicensed Operator Progression Af ter completing a license training program, many operators will progress to licensed positions. The licensed training programs are described in subsection 13.2.1. 8 13.2.2.1./ 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 9B. C. 3. d( 2 ). i 13.2.2.1/ General Employee Training (Badge Training) b elssseono,e

• XCl"A5U !nd$$i**1 **"Yf*llt l

%g GeneralTraining[$hk A. se /. All personnel including temporary personnel who are granted unescorted access to th VEGP's protected areag will receive the following trainin 4or, if they have completed a similar program at another plant or facility, will be tested to verify satisfactory knowledge of VEGP procedures.NRc, ,,,,e) gf,,,,c on de W *rs**'nsi auest list are iven<.vsgFs;/gr

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f Approximate acct 85 $. sed on fie NR.c frain 14e lind g't PfC8 L Duration Curriculum O General description of VEGP 4h facilities, general VEGP procedures and instructions, station emergency plans, industrial safety program, fire protection program, security program, mesel quality assurance Program, Rap s/,,7 (*M O 3, M Y tA$i bim wa.rm ci)ns, l L. All erso,nel shel ersa*,nel who *tt 30 u>ses cled accers +dinfe.ft/ht,$ eQ n &d%y o" i o4 !*Mio cadoviled a<ers JII necive H,e ake +rn '" f '*n 4*y w.ll)be..{ag,lar}ocoyra, loin fo k fol linly. er ,, h srocen orsell'shdl Ame e,7 'i n'a ,,,,4,ya 1s 4/es o g g ,,, y,,,,jf

yec. personnd abo are on Iht-MEC fc'3:nnel access list iven a. VEGP sifs sf:hfi mal ad jmded aceest v e. Q Ult.[ $ robn'ny $btf VL f'LLEVt on VEGP-FSAR-13 Approximate Curriculum Outline Duration Radiation health and safety 2h will meet the intent of Regulatory Guide 8.8 for personnel '/*didion con}reffed q* gjedr{c),,) m & 'Q who enter r;=t:ut;i ::c Regulatory Guide 8.27 and 8.29 are

1. dd"4* E4nct, gersonnd g/42 being used to develop the be.]airedYo[

se radiation protection portion work,, Q*J#h of general employee training. Material discussed in Regulatory esc 4WI w'ill Guide 8.29, Appendix A, will be % m add'Ip g Q f," covered except for Sections 17, 18, 22, 23, 24, 28, 29, and work -[ce, 4 m.aj. 31, since these sections would 4 be of little value to personnel in determining their risk from exposure to occupational radiation. 33 adiation worker training 4h Additional radiation work practices training will be provided for those personnel who are required to work in radiation-controlled areas without escort. 4, Respiratory protection training 2h for personnel required to work in areas of high airborne radioactivity concentration. 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.f Fire Brigade Training A. Initial Training Personnel assigned to any fire brigade will complete training in the following areas as designated by FSAR appendix 9B before being assigned as active brigade members. 13.2.2-14 Amend. 16 4/85

$1 VEGP-FSAR-13 Approximate Curriculum Outline Duration 1. Indoctrination of the plant 4 days firefighting plan with specific identification of each individual's responsibilities. 2. Identification of the type and location of fire hazards and associated types of fires that could occur in the plant. 3. The toxic and corrosive characteristics of expected products of combustion. 4. Identification of the location of firefighting equipment for each fire area, and familiariza-tion with the layout of the plants, including access and egress routes of each area. 16 5. The proper use of available firefighting equipment and the corrective method of fighting each type of fire. The types of fires covered should include fires in energized electrical equip-ment, fires in cables and cable trays, hydrogen fires, fires involving flammable and combustible liquids or hazardous process chemicals, fires result-ing from construction or modifi-cation (welding), and record file fires. 6. The proper use of communication, lighting, ventilation, and emergency breathing equipment. 7. The proper method for fighting fires inside buildings and confined spaces. ( 13.2.2-15 Amend. 16 4/85

VECP-ESAR-13

8. The direction and coordination of the firefighting activities (fire brigade leaders only).

9. Detailed review of firefighting strategies and procedures.

10. Review of the latest plant modifications and corresponding changes in firefighting plans.

B. Periodic Retraining

1. Meetings Quarterly training will be provided to each fire brigade member to review changes in the fire protection program and provide refresher training.

Refresher classroom training courses will be held for all fire brigade members every 2 years. (Refer to appendix 98, 9.5.1C3d, sections (4) and (5).) 2. Drills 16 Quarterly drills shall be performed, and at least one drill per year.will be performed unannounced toe determine the readiness of the fire brigade. Drills shall be repeated in sufficient frequency to ensure that each member of the brigade participates in at least two drills per year. Further, at least once per year a drill shall be performed on a "back shift" for each shift brigade. (Refer to appendix 9B, 9.5.lC3d(7).) C. Annual Practice Practice sessions will be held at least once per year for each shift origade on the proper methods of fighting ~ possible plant fires, and the use of emergency breathing apparatus under strenuous conditions encountered in fire fighting. Each member of the fire brigade will experience actual fire extinguishment on an annual basis. This may be done in the quarterly training sessions. (Refer to appendix 98, 9.5.1C3d, section (6).) D. Instructor Qualification Instruction of the fire brigade will be provided by qualified individuals suitably trained in fighting the types of fires that could occur in the plant, using the types of equipment available in the plant. Amend. 16 4/85 13.2.2-16 Amend. 19 9/85

SY 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. // Of.QET 13.2.2.1.6@' Quality Control Training Program b A r A. Initial Tra 1 Quality control inspectors who meet the requirements to y EEig77MAb be certified Level I in accordance with ANSI / 3 7~ 4 // qn N45.2.6-1978 will complete general employe'e training as described below.;TThose 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 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 N f 13.2.2-17 Amend. 16 4/85

.ws n o wr I a, a.. a. t. I I % I;Fy Coab. I Tra.hik 3 'P<.ya n A. ra % I i<a.a.~y i QusIety 6~ b. I in speJ, o a pe-u~~. L i u;i/ su e. 7' //e usi.,a-e olca A a edd' eg,serie~c e rejuven,e4. / idad i 4 Jc e<<Ab a' avr.2.4 -irrt pno, k y / ~,)/ i.o ws ua / py e c 7%. i r .he <e,u.-e d 71 e.:~p A A y e~ en / Afc e~p/o,<e -/<, a a, pre reja;<eareaA of sec A:s n.2. 2./.7 72 & n. a. 2. -i u;// Ane esn,s4 A d' is l & b a,~j aoh a A / a f4 X //e-l /a o, A-A syp.,,/ p,. ya, Au / fesAh,. A//'sw,a; 4e / /sa / , epa cc., espe <u--c / ~,w,,--. /// e.>,,,p A A a // n, Aa / A,6-; repia.e-,e~ h u,r/s ,ve a e./ ose o,9a-c d A f/.p..,;A.n. z : M / &a,hiy da // e os.c s f s f,a<e.ss uede / ua /e- <es c A< y1 A .r, h /~< < o /' p, C /,y eo s A / p A s f s,n A ~s es As asd <A da,ds as d o.a - the -jo A - 1',aih i y...

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[M VEGP-ESAR-13 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. Incumbents and New Employees i i 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 also accept prior training or experience to fill specific course requirements. Il

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13. 2. 2.1. 5!' Engineering and Technical Support 88Jonn y A. Initial Orientation Training n Professional personnel who do not have prior nuclear power plant experience will complete th f;M-w..i e orientation program normally during the first 6 months at VEGP. WN y ~ N #N"da/lan p %g Curriculum Outline f Approximate Duration C"%IJY of reyf M Q4 j General employee badge and health 6h f5/cs physics training af Industrial safety 4h Q ",#)' N New employee fire training 2h Med Reactor theory, health physics, 1 day Yr ,d and primary systems Primary systems, emergency systems, 1 day, g 8 k,shs/r w Q gj,, heat removal systems, and a radiation waste and monitoring Q r,/yg,[gEnis. g systems Mimtat 6A /

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13.2.2-18 Amend. 16 4/85

(d DE 6 VEGP-FSAR-13 Curriculum Outline Duration Heat transfer and fluid flow, 1 day secondary systems, electrical systems, and accident analysis Nuclear instrumentation systems, 1 day nuclear control systems, integrated plant control, and simulator plant operations 1 Reactor protection systems, safety 1 day injection actuation system, and simulator plant operations B. Continuing Training During periodic reviews of GPC's manpower plans, training goals will be established for professional employees to fill key supervisory positions as vacancies develop. C. A 1 13.2.2.2 shift Technical Advisor Training Program The shift technicab advisor training program is described in paragraph 13.2.2.1. 13.2.2.3 Mitigating Core Damage Training Program The VEGP training program for mitigating core damage is not a separate program but is integrated into licensed personnel training, pressurized water reactor senior reactor operator certified personnel training, and shift technical advisor training. Other personnel including the technicians, the managers of the Health Physics, Chemistry, and Instrumentation and Controls Departments, as well as the plant manager will complete training in mitigating core damage commensurate with their responsibilities. Avs,su.d Regualufsds*e,s Tnu*n,*y av Exes ion Tesfoy C.. Pummta,n.um/d f M e. * %g e an m L, af,;g,.,,, 4,;,,,;a -, q u y, ~ +0 Id emers"7 d dduke, nulidio,, yaded4,,, secary respirk roeabres. p w p 13.2.2-19 Amend. 16 4/85

VEGP-FSAR-13 13.2.2.4 Initial Position Job Analysis The training programs described in section 13.2 are the result of the initial position job 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 feedback to update our training plans or the position job analysis. Georgia Power Company stresses the use of this feedback to meet our overall training objective to train for job proficierrcy. Qg g g g 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 loadingg~~Almost all progiams in t a section are considered formal or " classroom" programs. A formal program consists of instruction in the classroom, laboratory, simulator, and field which is supervised by an instructor. Specifically, the shift technical advisor program (paragraph 13.2.2.1.() and the training (instructor qualification) program (paragraph 13.2.2.F.sff 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 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 in described in paragraph 13.2.2.1.#'. Io 13.2.2-20 Amend. 16 4/85

GZ VEGP-FSAR-13 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 16 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 subsection 13.1.2. If fuel loading is delayed, the continuing and requalification training programs as described in this subsection will be implemented to ensure personnel job proficiency. C g. 13.2.2-21 Amend. 16 4/05

b3 VECP-FSAR-13 TABLE 13.2.2-1 COMPARISON OF SHIFT TECHNICAL ADVISOR CURRICULUM WITH INPO RECOMMENDATIONS Georgia Power Topic INPO(h) Company (h) Education High school fundamentals 240 Note a College fundamentals 520 Note a Plant-specific applied fundamentals 120 120 Management / supervisory skills 40 40 Plant systems 200 200 {^ Administrative controls 80 Note b Ceneral operating procedures 30 Note b Transients / accident 30 Note b analysis and emergency procedures l Simulator training 100 100 Mitigating core damage O Note b Incore instrumentation Excore instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation a. All shift technical advisors will have a bachelor's degee in (. ) a scientific or engineering discipline, b. These topics will be incorporated into the simulator training syllabus. 0140V Amend. 16 4/85

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I Cinensisery j lesensneemt and Centrol 24 -h 15 l Esoseiset RAsineamence 24 j Reeseer Engineering 2 i ) . CONTINUtNG TRAINING i Hoehh Phy.iss/Redeo-25 chemisery Insenessent and Centrol 24 - Remineenense 15 Eleseteel h 24 ) Amend-16 4/85 l voorte TRAINING FOR NONI.ICFNSED 1 EtscTasc sessenATsees PLAser VEGP STAFF l CsCOl3lil M W unseri Asso useer a 2 FIGURE 13.2.2-1 (SHEET 1 OF 2) l fi A:ifr osse i

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f { GENERAL SYSTEMS ., J. TRAINING - a .!f 5 $8 [ 2 ~ l *- I Training lastructors 5 3 5' S I General Esapioyes 200 al 107 8. ,', { 5. n \\ H E Ei g Oiss tyCentrol 2 S I 1 3.f. a 3 9. Engineering & Tactinical a a a y Seapport 10 10 c o o m e v.n,_ r e. v a. a c 7 3 ag e (DfSCIPLINE SPECIFIC)J 4 j a-g. }: 1 -5MNOA445NTALSA = =N ~ i Training instruceers P 5 3 5 2 M )- o uesisy C e,.s s l Engineering Si Technical 10 Sispport 10-CONTINUING TRAINING m* gm3 Training lastructors 13 2 General Esapioyee 200 107 Quality Coneral 9 ,I e j r Amend. 16 4/85 , ~. voGits TRAINING FOR NONLICENSED g.' ILEcTaeC GENERATIteG PLAteT VEGP STAFF { 'l3 M VCf unset 1 Asso usesT 2 r D PIGURE 13.2.2-1 (SHFr.'" 2 OF 2) -; an* .f

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,.3 MONTHS TO FUEL LOAD S4 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 Pre - License Fuel Load operational Exams and Tests Criticality Types and Number o o of Personnel Health Physics /RediochewJstry (20) d_.- Instrument and Control (20) i Mechanical Maintenance (2C) ) Electrical Maentenance (20) = l Senft Technical Advisor and Reactor Engineer (6) \\ Nonticensed Operator (15) -= Training, instructor Qualification (15) General E-7:y:: (170) j independent Review Boards (6) Quality Control (6) Engirwenng and Technecal Support (20) y 5. TRAINING FOR NONLICENSED eoisitituwer.% EL CTRIC CENERATI.G PLANT VEGP STAFF 1 e c. s

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