Text

Forwards Proposed Draft FSAR Chapter 13,incorporating Draft SER Open Items 90-97 as Discussed at 841213 Meeting in Bethesda,Md.Draft SER Open Items 126-132 Also Addressed
	ML20106C260
Person / Time
Site:	Vogtle
Issue date:	01/31/1985
From:	Bailey J; GEORGIA POWER CO.
To:	Adensam E; Office of Nuclear Reactor Regulation
References
	GN-514, NUDOCS 8502120200
	Download: ML20106C260 (164)
	v • d • e

{{#Wiki_filter:Georgia Power Company Project Management Route 2, Box 299A Waynesboro, Georgia 30830 Telephone 404 724-8114 404 554 9961 January 31, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-514 Licensing Branch #4 Division of Licensing 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 PLANT - UNIfS 1 AND 2 DRAFT REVIEW COPY OF FSAR CHAPTER 13

Dear Mr. Denton:

Enclosed please find for your review five (5) copies of a proposed draf t for VEGP FSAR Chapter 13. As requested by your staff, this draft incor-porates Draft Safety Evaluation Report (DSER) open items 90 through 97 as discussed with your staff at a meeting in Bethesda, MD on December 13, 1984. DSER open items 126 through 132 have also been addressed. f A /'. If your staff requires any additional information, please do not hesitate to contact me. Sincerely, J. A. Bailey Project Licensing Manager JAB /sp xc: D. O. Foster R. A. Thomas G. F. Trowbridge, Esquire J. E. Joiner, Esquire C. A. Stangler L. Fowler M. A. Miller L. T. Cucwa G. Bockhold, Jr. I 8502120200 850131 {DRADOCK 05000424 PDR L-

VEGP-FSAR-13 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT -13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION This sectic-n provides information concerning corporate organization, functions, and responsibilities, participation in the. facility design, design review, design approval, construction management, testing, and operation of the plant. 13.1.1.1 Design and Operating Responsibilities The following paragraphs summarize the degree to which design, construction, and preoperational activities have been ' accomplished and describe the specific responsibilities and activities relative to technical support for operations. 13.1.1.1.1-Design and Construction Activities (Project Phase) 13.1.1.1.1.1 Principal Site-Related Engineering Work. Principal site-related. work such as meteorology, geology, seismology, hydrology, and demography has been developed and'is described in chapter 2. The-VEGP preoperational monitoring program is. described in the environmental report; this_ program establishes a preoperational baseline from which to evaluate future monitoring of environmental effects. heptoXirdy 30.0 13.1.1.1.1.2 Design of Plant and Auxiliary / Systems. An-evaluation of engineering progress of %&r4gpercent and overall completion of -4G-4 percent was indicated as of 3:nuary 19847 SG:1 .hycl \\ IR84 - 13.1.1.1.1.3 Site Layout with Respect to Environmental Effects and Security Provisions. Site layout with respect to environmental effects is described in chapter-2. Site security with respect to plant geographical layout and equipment is described in the security plan. 13.1.1.1.1.4-- Development of Safety Analysis Reports. Overall responsibility for preparation of the Final Safety Analysis Report (FSAR) rests with Southern Company Services (SCS) nuclear safety and licensing department. Preparation of the individual sections was assigned to the cognizant technical 13.1.1-1

VEGP-FSAR-13 groups within Bechtel, Westinghouse, SCS, and Georgia Power Company (GPC). 13.1.1.1.1.5 Review and Approval of~ Material and Component Specifications. All project specifications for safety-related equipment are reviewed in accordance with the quality assurance program as described in chapter 17. 13.1.1.1.1.6 Procurement of Materials and Equipment. As of January 1983 approximately 80 percent of the specifications for equipment had been awarded. Completion of this activity is scheduled for mid-1984. 13.1.1.1.1.7 Management and Review of Construction Activities. The Vogtle Project is organized on the project management basis whereby;all groups involved report directly or indirectly to theme >=fewrerwemryew who reports to the senior vice pre +,N Wtht (p_ 7 r-- E ':- t ,'- : iT-, : : - - ? -" _'_ ' h tA -- r y - - -.. _.., _... _..., weg h44 who in turn reports top: _ f -. _ _ _ t i c; '.:--- 1: ,___y TPz -. : : pr::iJ...^. .._. ;_:, ct ' E-kt4Io t-m"-'

' '^- "

"---- '_ - -- r.provides project direction to the ---d--* V u T <* i.a o. $uger ~___ _. .,___>_s_--- at the site. Monitoring and review o hv Sql ' g Y9' activities by construction at the site are as follows: Leged ' ,gpgd < _- ; - ' - - - -,___ provides the A. The field operations group under the direction of the [1'p ^ l GevotAL fg - - __ day management and planning of the actual y,'4I' _mm--.... M AVA&E 4 day-to-physical construction activity onsite. {" B. The quality control group under the direction of the 'Pg*kg. . {D g y

surveillance and inspection of the construction manager-quality control provides quality control k

activity to ensure that good construction practices are followed and that design and regulatory requirements are adhered to by the contractors. C. The project cost / schedule group.under the direction of the manager-cost and schedule provides the project cost and schedule control program and its implementation through the project organization. The group also monitors contractor cost and schedule performance to keep management informed of project status. It provides objective data to identify construction problems early so that alternatives can be developed by management. 13.1.1-2

VEGP-FSAR-13 D. -Support operations personnel control material and . equipment availability and ensure that documentation is complete, current, ar.d retrievable. ~ 13.1.~ 1.1. 2.Preoperational Activities 13.1.1.1.2.1 Development of Human Engineering Design Objectives and Design Phase Review of Proposed Control Room Layouts. _The VEGP control room was designed according to mid-1960s~ design criteria except for a reduced size centrol board..The design incorporated the human factor design criteria at that time. An independent evaluation on human factor-design has been. performed on a mockup of the control room. .A detailed discussion of control room design review and-human engineering factors is described in chapter 18. 13.1.1.1.2.2. Development and Implementation of Staff Recruiting and Training Programs. The operating staff is described in subsection 13.1.2. Recruiting of personnel to fill these positions started in late 1979. . Training programs have-been developed for this facility and are described in .section 13.2. GENECM. (DeuAGER VcqMt., NyedeMt. O phit *l MYN 13.1.1~1.2.3['DevelopmentofPlansforInitialTesting. The .;1--' ---, ,is responsible for all aspects of the initial test program of the VEGP. As part of his responsibilities, the GFAVMt r'==*

r (or his designee) will direct the development of

.the startup manual. The startup manual will define-the startup organization, define the: responsibilities of involved organizations and personnel, ' delineate the qualifications'necessary for;startup personnel, ~ and contain the' administrative controls necessary for the implementation of that.part ofuthe. initial test program prior ~ to fue1-load. So, gegeg 3 FM G4MH IL b 2.1.5 Nr. g ogww,o PJ o r r4E.. h th u. TP5.T g"'Rb(,h % The administrative controls, qualification for testing personnel, and other required procedures for conducting that part_of the initial test program after-fuel-load will be Lincluded in~.the plant procedure manual. L 13.1.1.l.2.;4 Development of Plant Maintenance Programs. The work force assigned to the VEGP.will provide qualified 1 maintenance personnel prior to initial fuel loading. 13.1.1-3

r "v s: r2A:_, Structures, systems, and compcnents that prevent or ritigate the : nsequences of postulate accidents that could cause undue risk :: the health and safety of the public w;11 be mainta:ned in ac:Ordance w :h the quality azsurance program. The maintenance staf f w' l_ be sized :c perform the routine and preventive maintenance w:rkload. The staff will be supplemented by outs:de centracters as deemed appropriate by plant manageren:. Maintenance is performed under the direction ^# -^7 '-=^' euperv ors and in accordance with accepted work pra ::ces. The scope and frequency of the preventive maintenance will be based on past experience with similar equipment and the manufacturer's reccrmendations. Records will be kept to establish the maintenance history of major safety-related . equipment. Maintenance and repairs will be performed by qualified personnel in accordance with written work orders, maintenance procedures, standing orders, vender technical manuals, and/or applicable codes and regulations. Qualified maintenance personnel will possess the skills to perform work without detailed written procedures. Except for emergencies, maintenance work will be preplanned. Training meetings will be held to foster safety awareness and quality of workmanship. 13.1.1.2 Technical Support for Operations Technical support for the operation of GPC nuclear power plants has been established and is in effect for Hatch Nuclear Plant. For VEGP the same organizational technical support will become available prior to the' start of the initial test program. 13.1.1.2.1 Power Supply Department The executive vice president power supply is responsible to the president for the operation and construction of electric generating plants. He has reporting to him the amuser vice qqg( president-engineering, con management, __, gM senior vice presiden* gtg'g g og, and project the W---..Jfthe general fhwe M manager-fue;. services, and" tne%S_'.$.qt:n t..ana g e r-qu a ~ii t y g .a. g assurance - "' r ' 11 2 The quality P1 V0; 2 assurance organization is described in chapter 17 The principal organizations in.the power supply engineering and udstatTud l-services department previding this support are mechanical . engineering, civil engineering, generating plant electrical ' engineering, engineering services, and environmental affairs. W Eustsulms Mo comwqu' W(LES KCwpe. TW!owER. Sypl4nt prov. des anv intmem GG The power hupply engineering services depar.m uc interface through which the plant staff may obtain assistance OMTl(Thd $ifflCE3 Wb+1b poi ..t. 7. '. _ c. L u-

VEGP-FSAR-13 from engineering, construction, procurement, SCS, and.other ~,. outside engineering organizations. In addition, environmental r affairs manages and coordinates the overall environmental programs to obtain permits and licenses from state and federal agencie g samas cThe 7---'i_,, constructiongdepartment can supply . technical support when requested to manage field operations for civil, mechanical, and electrical construction work. The power generation services department provides support serv'ces in he testing, installation, and maintenance of plant cont is and stems and irects p war gene ation la ratories fos il fuel, environmen al, and lant sam ling fun tions. T. nuc ear gen ation sec 'on has e ineers provid li nsin support and to rev'ew selec d activi ies wit n the powe gene ation d artment. hey serv as the ompany interface w h SCS i the area f fuel ma gement, fuel procurement, nd repr

essing, on request, the nuclear ovide technical support in broader

( generation section can areas, including health ysics. f' t - _ t :.t : --- -^4

^ " - _ _ J... _ _ _1 : ;,- - -- t -- En 1

T asse vs.s. i.2. i 13.1.1.2.2 Engineering g onstruction4 c 1steo %S " _ _ j : : 1 M _.., _. - - '_ Department The shammer vice president-engineering construction," N c,_1 .._.,_-...; provides overall direction and control of the various engineering disciplines to ensure timely and effective accomplishment of assigned projects. ":;;.- tin;; to g .w- .4__ ____2 2__m __2 _w4mc o m, 4. _ _. _.. - - ~ ~ E'!Eeat' W I+in" J.._ A_ __ .4_ L__ _ C_li- _f.~ _~', ",_.." _'#, -m.e._ -.y..~uw .,,,,,,,,._,._____2 _ 7,_, _ _ w _.. _.- 4 ^ is duties include coordinating the engineering efforts f architect-engineers, suppliers, and outside consultants. In addition, he may obtain technical assistance from SCS upon request. c.. M el-to4 13.1.1.2.2.1 ? - - ^ _ _._ 1, Enginee.ri_ng _ar>riAServices Department. the GPC power supply organizatio%Ni'Vfdss' department is part ofTg g pa The po'.'er cupp-ly engineering and n. the vice president-engineering and services and consists of n 3 various groups, i.e., engineering services, engineering, and environmental aff airs. AThe re OrcuPs report to the 'Jice p r-e si dc.s and chie f m.ginc c r - ac"a r r"='g' "'andNd.ee r 4 ""NcTI" 'nd e=~4" a ser"4c e.The power supply engineerin organization chart is shown in figure 13.1.1-2. O.- }(M'D.iful y b Eu.e pn d <n puuiMoq wk.cmsh. M g, ~13.1.1-5

\\ Insert 13.1.1.2.1 In addition, the Power Supply Department includes the Nuclear Power Organization. The Nuclear Power Organization includes the Nuclear Operations Department, which will be responsible for the operation tof VEGP. This department includes the Nu-clear Generation Engineering Staff, which provides support in the areas of regu-latory responses, generic issues, long-term planning, health physics, emergency response capability, nuclear training, refueling operations, and general angi-neering. The Nuclear Power Organization is additionally responsible for m oage-ment of Nuclear Construction. Outside technical support to plant operations outside GPC will be provided by SCS Civil and Architectural, Mechanical, and Electrical Design Disciplines, and the Nuclear Plant Support Department. SCS Nuclear Fuels Department also provided Nu-clear fuel contract administrative services, and the Nuclear Safety and Licensing Department provides reload licensing and operating licensing support. Additional outside consultants will be used to provide technical support on an as-needed basis. Inser 13.1.1.2.2.1.1 Mana r of Engineeri o Services The manager-engine ing services is responsib1 to the vic president-gineerin -anjconstruction rvices throu the vice pr ident and lef engine -power s ly engineeri and service. Engineerin services i responsibl for secur' g managing al engineering pport involv' g design, ocurement, and constrt tion the compan s operating clear, fossi, and hydro electric ge erating pla'ts. gineering s vices mainta' s an up-to-d e status o all phases of the desi cessary pl nt addition, ocurement, nd construct ~ n services r quired for f dification, and enviro ntal retrof' s. / / The manage of engineeri g services d' ects the en neering sfvices organfzation in perfo ng the follo ing function. f / 1. Providing a 'ngle interf e through wh ch the p1 ts may obta engi-neering ass' tance / / f 2 Ensuring atengineerig,procuremen[,andcon/tructioneff[rtsare directed oward meetin theneedsof/theplants / l / / / l 3. Obtaini g and report g the status pf engineering, procur nt, andcon-struct on activitie / 4. Coor nating the a tivities of t variou agencies in Ived in respond-ing o plant requ sts for engin ring as istance 5. Pr viding for the orderly flow of info ation betwe the plants and the . ion services department i engineering arn v. l

VEGP-FSA.R-13 ""he primary function of the pcuer cup,cly engineering and Con!<vc4 % services department in support of the power supply organization j and other GPC operations includes: A. Providing engineering and technical support for the operation and maintenance of existing electric generating plants. B. Overall project management and engineering services involving design, budget, procurement, licensing, construction, and startup of retrofit projects for GPC's existing generating plants. C. Participation with SCS and other GPC departments,in the planning, scheduling, budgeting, and performance of engineering and licensing work for GPC's new generating plants. D. Direct and indirect technical and/or. licensing interface with various environmental and other governmental and regulatory agencies and concerned public groups The educatN nal background',icA N EY ' kt7 E k

C #an Ee M D5 eqYe N amer,Qek, years of nuclear power plant associated work experience, pnd total years of engineering or

%=5 e o%n science experience of the 14)2rgraduate engineers and scientists in the power supply engineering and services department as of [ " pt;;bsr 1, 1001, are as follows: gg %nvarj 12.,1%s A. The number of graduate degrees: baccalaureate - 44t; masters - P.

Doc.4em4e _1 IM f

y-bed i3. l. \\.tl.t -B. The t tal nr. fc2r of nuclear pcucr plouw e s s o c l o wei.1 .crh engmitencc 290. C. '"hc tet:1 man imou e vi e.wiusuulug or wientific-vf :.his cicctricel utilli.y 0".perience - 1900, peu uva ei-icnt;d - 120?r. D IEl \\ ~2-.7 I{ lh

2. 2. l.{.1 13, l. \\, 2.,1,2. j 13.1. l. Z. L Z. l i % 13.).\\.1 Z.3 13.1.1.2.3 _ b d a loow.l.

.a _ _ _ -... n__ Department sNc\\tn opv.b4 ;n dggtmeggnder the supervision of -the The 7...__ ,...-.i N r^__ti r has the direct senior vice president m responsibility for the operation and maintenance of ::4_h GPC'> Nuclear Plants ~d

" in; 'r1:n:_ vi vi c..

Support may be .provided to the NS M1 [UN'*N " department by other GPC and administrative Tec g Q,m,g g,eering, departments. e department general office personnel of the p _.

w. mum m a o',

as $. persons qualified on E2 ~ h e staff consists of 5% h ge,q follows: y (St L'hv sovid i i $ 13.1.1-6 ~-

[ Inssrt 13.1.1.2.1 L ^In' addition, the organization of the Vice President, Engineering and Construction Services is providing pre-operational and/or start-up support / in the following areas: a. Development of 53 pre-operational test procedures b. Computer software support in the area of Vogtle 1 and 2 ERF Computer c. Qualifications of Class 1E motor insulation d. Simulator facility e.~ Meteorological Tower replacement f. Fire fighting procedures g. Pollution control facilities (cost estimate) h. Environmental licensing interface with agencies and public groups i._ Collection and analysis of samples for the radiological (biological and water' quality) monitoring program. f Insert 13.1;1.2.2.1.1 Engineering and Construction Services - The - manager-engineering and construction services is responsible to the vice president-engineering and construction services. Engineering and Construction - services is responsible for-securing' and managing all engineering support -involving design, procurement,. and. construction for the company!s operating nuclear, fossil, and hydro-electric' generating plants. Engineering and Construction services maintains an up-to-date status Ton all phases of the design, procurement, and construction services . required for ~necessary. plant additions, modifications, and ~ environmental retrofits. The manager of Engineering and Construction services directs the engineering services organization in performing the following functions: 1. Providing a single -interface through 'which the plants may obtain engineering assistance. 2. Ensuring -that engineering,. procurement, and construction: efforts are directed toward meeting the needs of the plants

3. _0btaining and reporting the status of engineering, procurement, and construction activities 4.

Coordinating the - activities of the various -agencies involved in responding to plant requests for engineering assistance t' 5.- Providing-for ~ the orderly' flow of information between the plants and the engineering and construction services department

6. 'Providing procedural, accounting, cost reporting, and other

' technical services ' required by the engineering and construction -services department 7. Maintaining' a qualified. suppliers list for nuclear plants - and _providing related procurement assistance'as required r

Insert 13.1.1.2.2.1.1.1 p c coalsTut'floA) Vogtle Project Manager. Reporting to the manager-engineering 4 services the VEGP project manager will be responsible for performing the following functions: 1. Securing all engineering services by analyzing project requirements and assigning engineering responsibility. The project manager is the interface for GPC with BPC, SCS, and Westinghouse in the design and construction of VEGP and, as such, ensures that' action or response requested by the participants is made by the proper groups with GPC. Th ject ma r keeps the vice president,EamyL informed co -sku.6 n of project status by providing status repor s, w in icate Se.vm s problem areas; in addition, he makes suggestions, as necessary 2. Serving as.the principal interface between the Vogtle plant staff and the GPC power supply engineering, construction, and procurement departments, SCS, and/or outside architectural / engineering organizations to ensure coordination of all phases of engineering, procurement, and construction support required by the operating plants 3. Securing, reviewing, and providing conceptual designs ppgajeg costs and estimates for the Vogtle manager-engineerin tFie development of plant budgets and preparation of genera work orders and plant expenditures 4. Participating with the Vogtle plant staff in reviewing and approving engineering designs, cost estimates, and specifications to ensure that they are responsive to project requirements and in compliance with established company guidelines 5. Reviewing and approving procurement related documents developed by GPC power supply engineering and/or SCS 6. Monitoring project engineering, procurement, and construction l progress to ensure that project schedules are met and to ensure that budget and cash flow requirements are met 7. Participating with the manager of environmental affairs and/or other appropriate engineering agencies in order to secure necessary permits, licenses, and tax exempt pollution abatement bond financing l for applicable projects 8. Developing and submitting status reports to power supply management l and the Vogtle plant staff on all project engineering, construction, and budget matters on a designated regular basis 9. Assisting in the coordination and development and implementation of startup of new facilities and equipment to ensure the initial satisfactory operation of such equipment i

10. Continuously participating with the plant staff (s) and the appropriate I

engineering agencies in evaluating the performance of facilities I and equipment I I

r Insert 13.1.1.2.2.2

- d Engineering. The manager-engineering is responsible to the vice president-engineering and construction services M"ch the 'f:: p ::f tnt and + 0f :.,.acer puwei s t' aagi--~4 -- M r,. kes.

Engineering, comprised of the civil, mechanical, and electrical engineering divisions, is responsible for providing engineering support involving design, procurement, construction, and implementation of projects related to GPC;s fossil, and hydro-electric generating plants, and in non-safety related applications to nuclaar plants. In fulfilling these responsibilities, the manager-engineering performs the following functions: 1. Directs the civil, mechanical, and electrical engineering divisions in designing new facilities, modifications, and additions for generating plants and other company projects 2. Contributes to GPC's overall technical competence in engineering design by providing technical advice and assistance, as requested, to other engineering areas ..g... , v WW 3. Ensu/es compliance with all appropriate regulatory agencies in matters of engineering 13.1.1.2.2.2.1 Chief Engineers. Reporting to the manager-engineering, each discipline engineers civil, mechanical, and electrical has the following responsibilities: 1. To manage engineering activities associated with the evaluation, design, material procurement, construction, and implementation of necessary projects for new and existing generating plants 2. To manage the activities associated with the evaluation of design alternatives and the recommendation of solutions to design problems considering factors such as costs, schedules, reliabilit/ and operating requirements, and technical feasibility for nor-safety-applications 3. To direct the design of systems and components to assure a high level of plant productivity and engineering principles 4. To ensure that all engineering design drawings and specifications prepared in the division are based on sound engineering principles 5. To participate in planning to determine the location and type generating plant and plant equipment to assure the availability of electric power when needed 6. To provide assistance to other departments of the company concerning related engineering matters which may contribute to the overall efficiency, design engineering, construction, and operation of generating plants 7. To maintain complete records of planned and existing hydro-electric plant sites in Georgia to aid in managerial decisions (chief civil engineeronly)

- 8. To establish and-implement division policies and procedures as. required to assure that power supply engineering and services will meet its engineering support objectives. 13.1.1.2.2.3 Manager of Environmental Affairs. The Manager of Environmental Affairs is responsible to the vice president-engineering and construction services. h +ha "f:: ;;r;;ident a. d d.icf : ;f : r ;;; ;,

3. ppb ;;;i : -ing

+ h-~ $

;;r. n es. The section is responsible for managing and coordinating GPC;s overall environmental program principally for generating plants, to assure compliance with state and federal environmental regulations in design, construction, and operation of these facilities. Environmental affairs coordinates and obtains all environmental permits and licenses for generating facilities from the State Environmental Protection Division, U.S. Environmental Protection Agency, U.S. Army Corps of Engineers, U.S.

Coast Guard, and the Department of Energy. Environmental affairs also directs laboratories in conducting tests, surveys, studies, and analyses to ensure that generating facilities comply with environmental regulations. In performing these services, environmental affairs provides a single inter-face for communications with outside agencies _regarding environmental matters. ( i

4 VEGP-FSAR-13 A. The number of graduate degrees: baccalaureate - 4 masters _6.S Z$ 1 i B f. The total man-years of nuclear plant experience - g The c:ructure of the general of fice p;_dene. bsr_ *'. Mo r :^--*= department am staffisshownonfigure13.1.1-/anddescribedinthe following paragraphs: 3 kNdtp. bem. ^^-^ " *d - The 13.1.1.2.3.1 Senior Vice, President-2:. senior vice president-f *fT 5."" '- - ' T is responsible to the 2 executive vice presideng gg supply for the safe, reliable, maintenance of :11

t'---

and efficient oper g g, ,C ---- GPChg- - ife works closely with the other departments to ensure that the plant design, construction, and operation are carried out efficiently and safely. .1 e President 2 _A ^.~ m1

".____k__

Fossil d Hy A.4 __;a. All fos and hydro / enerating pl tg g, me ugr the giministrative gtg:-- (: og th vice presid t He reports o the ossigaqdby __r. nior be pre den dl:Y C-- 'T* [ - -m power tion are ea' assigned / sponsi lity r a design ed group of/ enerating pl ts. ' e mana rs of ower gene. ion are res nsible to t vice p siden 1" -____1_.. ,..l_ jmwssts n-_ I m R& O l r

w m.

l A. per sion of o ration and, intenance oQ 11 ip ht in th GPC generat g plants. / B. hed ing equ ment outag' to be compat le wit ste load d ands. / C. or nating, ith the e, ',neering depa ent the ns uctio f new equ, ent to satis GPC operating qu ement' / I / D. ec al a,' gnments a ' required. I i k f sedioN 14t Lo@TE.D 13.1.1-7 ~ -.

VEGF-FSAR-13 13.1.1.2.3.3 Manager-PowerOenerationSer/ Ices. The nager-power gener tion services s responsible .o the senio vice president-ower generati and has the ollowing responsi.lities: r A. To protide - 'utionstosp/cificproble.m/arisingat generating,lants. f f To orovi e technical sp/'ialization kh the areas / B. ec /recipitators,jfire protect ^on, f combus['onturbines, oiler and turpine maintenagte, water che istry, steam and c6mouter servic4s. )/ / / / To/ provide manage $ent r fossil fuels includ ng of C. ipventory contryl, sampling, ahalysis, and uality control. / / / / t D.j' To provide *gchnical upgrade training for new employees a,t generating plants. / / To origin &te and maint/in a system op' general fos 1 E. plant opsrating and ma'intenance procedures. F. For power systems engineering. -l l l f / l Protective reIaying and ass,dciated devic s. 1. / PSCC coordihation. Powereg[pmenttesting-High-pot, igh current, 3. etc. G. For selection of plant t chnical personnel, chemists, technicians, and enginee s. (g..;r2tirr.pdlVicePresident 13.1.1.2.3. and General Manager-Nuclear l-The vice president and general manager-nuclear emeneteen is responsible to the senior vice president-m bden hm b ,_..--___.. for the safe, reliable, and efficient operation of ^ all nuclear generating plants in the GPC system. 13.1.1.2 3 Manager-Nuclear C $ en. The manager-6 general manager-nuclear g_..gc,tly tyg vice president and nuclear .g.... t s. reporgsg _____;a.A_____ of each nuclear plant in the GPC system report directly to the manager-nuclear eJonseemoon. OMoe 1 L l 13.1.1-8 l

VEGP-FSAR-13 E %det En uta9 AO M a gtN du b E ^9;afthe a 13.1.1.2.3.[.2 NfNuclear ngineer. Theghief nuclear engineerreportsgjigggglytothevicepresident and general - g - "^- of the nuclear manager-nuclear k YAs mana e division, the4N I._ E hYnIE8r the following responsibilities: A. Providing regulatory and licensing support for the operating nuclear units. B. Documenting licensing contacts with the U.S. Nuclear Regulatory Commission (NRC) and maintaining files of all NRC correspondence. C. Interfacing with the appropriate companies and organizations in the areas of nuclear fuel management, procurement, and reprocessing. D. Evaluating and preparing amendments to the plant operating licenses and FSARs for operating nuclear units. E. Preparing and maintaining plant security and emergency plans, including necessary agreements with state, federal, and local agencies. F. Addressing safety evaluations and unreviewed safety questions for design changes to operating units. G. Preparing an annual report on the environmental impact of radiological releases from the operating nuclear units. H. Providing any other technical, licensing, or nuclear expertise, or onsite technical assistance that may be required. he4 IS.I.i. L. 3. 2. 2.. I S.l. l.2. 3. Z.1. 2, Ao 8 1. l L 3. 2 L 3 j 1 .1 2.3. .3 uc1 ar Li ensi an Suppo En ine s./ Tp e li ensi g a sup ort gin rs re rt ot die 7 1 r e gine r a ass st h in e dis har e of his resp nsibilit es as listed above. 3 13.1.1.2.3./z 7 Manager-Nuclear Training. The manager of nuclear training reports dire tl to the vice president and The responsibilities of general manager-nuclear,,- a = this position are as follows: A. Providing the preparation and conduct of training programs at GPC nuclear plants and training centers to ensure compliance with NRC regulations and Institute 13.1.1-9 e

4 13.lil.2.3.2.2.1' Manager-nuclear regulatory engineering

Themanager-nuclearregulatoryengineeringreportstothemanager[egDer-

'ing-and chief nuclear engineer and is responsible for providing plant. support Lin the areas of licensing, NRC compliance, legal considerations, and fuel management. The manager-nuclear regulatory engineering is responsible for maintaining the 1 operating licenses, Technical Specifications, Environmental Technical Speci-fications, and Final Safety Analysis Reports (FSARs) for the operating nuclear ,~ plants, and for managing all changes to these documents. This individual is responsible for submittal preparation of correspondence to the NRC regarding 'the operating nuclear units. This includes. responses to requests for infor-mation, responses to NRC Inspection and Enforcement Inspection Reports and bulletins, and comments on proposed regulations. -The manager-nuclear regulatory engineering is responsible for fuel management . activities. These responsibilities include establishment and maintenance of a fuel procurement policy and management of the implementation of the estab-lished policy.- .13.1.1.3.2.2.2~ l Manager-nuclear engineering and evaluation ~ .The manager-nuclear engineering and evaluation' reports to the manager-nuclear . engineering and chief nuclear engineer and is responsible for providing plant support in the areas of retrofit and generic engineerina, special engineering _ activities, and plant operations support. This supp -

ected towards ensuring compliance with regulatory requirements assus.iatea with backfitting and assurance of safe, efficient plant operations.

- r

13.1.1. 2. 3. 2. 2. 3.

The manager-nuclear operation analysis -The manager-nuclear operations analysis reports to the manager-nuclear engi- .neering and chief nuclear engineer and is responsible for. providing support for operating nuclear plants in the areas of nuclear plant operations analy-- m sis licensee event report (LER) review, generic.~ review, safety evaluation programs, probabilistic risk assessment, and accident analysis. This indi-vidual:is responsible for conducting reviews of plant maintenance trends, + ~ surveillance trends,_ licensee event reports, and other incidents, and devel- _oping solutions to problems in these areas. Dis individual provides plant ~ support to ensure compliance with' criteria developed by the INPO. [ IIntheareaofLERreview,thenuclearoperationsanalysismanagerisres-

ponsible for development of interpretations and corrective actions concerning

.- personnel errors, component failures, and repetitive events. Included in this respons.ibility.is the review of generic events provided by INPO, Nuclear ~ Safety Analysis Center (NSAC), NRC, and other outside agencies in order'to imake:reconnendations for action to be taken by the nuclear plants'. The . manager nuclear operations analysis-develops trends and analyzes root causes a for these events.' u -..

r 4 -VEGF-FSAR-13 of Nuclear Poweg g agi g gNPO) standards, and ensuring that pouc. ,_..:ra.__. personnel have the education, training, and skills to safely and efficiently operate and maintain the plants. B. Administering the utilization of the planned plant site simulators by both GPC personnel and those from outside organizations to maximize the utilization of the simulators. C. Maintaining the modifying GPC simulators to provide the most cost effective training and ensuring compliance with NRC regulations. D. Staffing and maintaining a group of qualified instructors who are capable of teaching all aspects,of nuclear technology including plant operations, electrical and mechanical maintenance, health physics, chemistry, and control and instrument technology. E. Ensuring that all training programs and materials are documented to comply with NRC regulations and INPO criteria. 13.1.1.2.3./.4 t 5 Manager-Nuclear Planning and Control. The manager-nuclearplarningandcontrolreportsdirggggytothe vice president and general manager-nuclear fE*#8 The responsibilities of this position are as follows: A. Providing for the long range planning and scheduling' of maintenance work to be performed at GPC nuclear plants in accordance with the long range manpower plan for the nuclear area to ensure that commitments made to the NRC and company management are met and the nuclear plants are adequately staffed. B. Monitoring the financial activities of the GPC nuclear plants to ensure their adherence'to approved budgets and to provide GPC management with information from which to make sound decisions concerning expenditures in excess of the approved budgets. C. LProviding input into the CPC nuclear plants' security efforts from a nuclear generation viewpoint to ensure that changes made.by the organization in the physical or manpower makeup of the plants are integrated with the efforts of the security organization. D. Serving as GPC coordinator with INPO for the purpose hanc* *"d 'T"* 12f@t? 13J4%PM MaM*AE ja.*"bMb bf" kMgn th* p p,, A Nre%q j e M k h on d.(N 4 Vit W i k M R y gut

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4 VEGP-ESAR-13 3 Tnse,A e,g,1,1,3.t.s, 13. 1. 1. 2. a. 1. (,, s. t. i. 1,4,13.1.t. 1. 4. j w, 13.l.l.3 13.1.1. Corporate Management Georgia Power Company operates electric generating plants with an aggregate capacity in excess of 14,000 MWe. The company has experience in the design, construction, startup testing, operating, and staffing of modern generating facilities,. including Hatch Naclear Plant, a nuclear power plant with two boiling water reactors. The corporate organization, which provides the line ' responsibility for the operation of the VEGP, is shown in figure 13.1.1-1. The ultimate responsibility for design, procurement, construction, testing, quality assurance, and operation'of the VEGP rests with the president. The president assigns responsibilities to the various organizations as described in paragraph 13.1.1.2. Members of the corporate headquarters staff available for the technical support of the Vogtle Project possess that' 4 - combination of education, experience, and skills commensurate, with their level of responsibility, providing reasonable assurance that decisions and actions during the design, procurement, construction, testing, quality assurance, and operation of the VEGP units will not constitute a hazard to the health and safety of the public. The operating organization for the VEGP is described in subsection 13.1.2. The company technical support organizations i 'for operation, modification, and maintenance are described in paragraph 13.1.1.2 and shown in figure 13.1.1-2,$' I-3 ** G l.L -%g / L [Theresumesofselectedcorporatestaffmemberswhoprovide [h technical support for VEGP are show in table 13.1.1-1. Nrt. et aJO pladyteum5es 'm h her)t d W8 !N at btk lomb'0 13.1.1-11 Amend. 4 2/84 L A

Insert 13.1'.1.2.3.2.5 and 13.1.1.2.3.2.6 13.1.1.2.3.2.5 -Manager-nuclear chemistry and health physics 3 .Thelmanager-nuclear chemistry and health physics reports directly to the 'vice. president Land' general manager-nuclear operations and is responsible

for providing~ plant support in the areas of emergency preparedness, radiological environmental assisment, health physics, radiation = protection,

. plant chemistry, radwaste, and radiological health. safety. 'If the area of emergency preparedness, this individual has overall responsibility for preparation and maintenance of the Emergency Plan. This Lincludes. the. development and implementation of emergency drills and exercises; federal, state, and local interfaces; and public information program's.

Aaoitional-responsibilities are for coordination with offsite medical" ; facilities, development of new emergency facilities, public notification systems, and corporate emergency plans.

The management of radiological environmental assissment activities ' includes 4 thet.following regulatory requirements for environmenta.1 monitoring, ~ assissment, and reporting as required by federal regulations, and analysis of routine and, unplanned releases of radioactive materials.

m lIn; the areas of health physics, radiation protection, plant chemistry, and radwaste', the manager-nuclear chemistry and health physics is responsible

~ _ fori overall ' support of plant programs, including program upgrades and ~ ' improvements. 13.1.1.2.3.2;6-The manager of nuclear performance e /The manager of __ nuclear performance reports. directly to the vice president and > general : manager-nuclear operations and is responsible for providing nuclear plant support in the' areas of nuclear performance, such as: W .1. : Manage' the activities of the nuclear performance department in e . providing _ support services - to the nuclear. generating plants in the preparation of. nuclear goal formulation and nuclear performance =, evaluation to ensure that the' nuclear plants are operated : safely. -and economically.- ~2.. Track events' = of safety significance' and such items as nuclear . ~ lant sapacity. factor, plant availability, forced outage rate,_ p and heat = rate. p ~ '3.. Coordinate the nuclear - plant reliability data system. to ensure full 111mplementation and _ participation 'by; all operating nuclear- ~ . plants.: 4.-LMonitor maintenance productivity and performance to develop programs-

to' improve productivity.

5.=' Develop,

direct, and. coordinate.a nuclear plant performance

.' monitoring program to maximize unit efficiency and' nuclear plant

productivity at each nuclear" generating facility.

n

VECP r W A. 'The number of graduate degrees-bacca ureate - alib, masters - 6. ZZ 8. The total a-s of r+ g o io a 1 m _n c S41. 3 p(. The tota man-years nucle plant experi nce - M. 2.2 s The structure the gener offic p$$$ M b '^s department staff is show on figure 3.1.1-2 and described in the i following pa agraphs: [4 TI}e/ %dm m. 13.1.1.2. .1 Senio Vice,P sident-T:1:r 7 - H ^m senior ce presi nt-f""_~ /".""_ - ' ^r is responsible tc( the iexecut've vice p esiden,t-g gy supply f the safe, rpiiable, i d a maintenanc of til ~ ^ - " - r -- -ficient o er g oPCS m

g g he works osely with the other t' _

Ee' rtments o ens'u M that the plan design, construction, an# o r

ion a e carried out efficie ly and_safekf.

/ L $6 hot 13.1.1.2.J 4l 3Vice President 2..l _.- l M_.._,__ Fossil a_nd Hydro Semmrteen. All fossil and hydro generating plant g g 3g come under the administrative corg:ogog the vice president fossi {agd h,yg g r.:rr- -. He reports to the m..__11 ,r. I'responsibility for a designated group of generating plants. - The managers of power generation are responsible to the vice '-~ i A 'tewit mwacy.a F u. l,, g@ o pmb,.., l_ - - - ' ' ~ - - - ' _____1 _... l ' t--- ^ president .__ r _ A. Supervision of operation and maintenance of all equipment in the GPC generating plants. B. Scheduling equipment outages to be compatible with system load demands. C. Coordinating with the engineering department the construction of new equipment to satisfy GPC operating requirements. D. Special assignments as required. Mseth G. \\.\\. 7.. 'l. t 13.1.1-7

m\\~$.I.1.3.4.I 'Ihe Manager, ifydro and Power Generation Services has ass.1med the responsibilities previously held by the Manager, Power Generation Services. Reporting to the Manager, !!ydro and Powe Generation Services i is the Manager, power Generation Technical Services, whose organization provides technical mapport in the following areas to fossil-fueled, hydroelectric, and, to a limited extent, ruclear generating plants: a2pplementing the plant engineering and technical staff to assist a. as needed in resolving eatipment problems and informing management of industry experience and developments, b. Power systems engineering in the areas of protective relaying, easignant evahlation, and special testing. c. Assistance in conpater hardware selection, installation, and maintenance, as well as software design, d. Development of water chemistry analytical procedires, chemical cleaning procedsres, environnental policies and procedsres, and performance of environmental testing. e. Operational data analysis, plant performance program development and implementation, maintenance sche &111ng, ard specialized-expertise in precipitators and barbine-generators. ksof Snw 1 h 1 % 5, % e q o m t M so 4 d % ( % acte / h '0 6 F-f s a s uasmaus,A 6.<eso-1 w aemklde e e rma s\\1 kB b %. 50 pwaiso e, ha. %dto A y bbucM sumus wi46_ sopexmor, TechnicJ 5 ecsd, dion, p % h k 3\\ m0sokoks kurag% h\\\\wsg }sksUssus. 1 Gby.L.yu.s. a-

hc.daucesk. : vf thkes.

J Lns%.6de. 1 o b. IaN nnn-jeurs oh eqws exq, t79 hS&tbwe.oldk.Fon,l.mlifyvhl ss shawa on Frp-(3. l. l-4 _ _..___ _.

13.1.1.3 QA Department The Opfr vice president - A is re@sponsible functionally to the executive nan 4 vice president - powg_A to m The executive vice president has authorized r,s 1 thevicepresident7*Q age the QA program for design, construction, testing, operation, and maintenance and to ensure its implementation in accordance with the requirements of the QA manual. The QA department is uarters and at each plant site. The QA corporate headquarters staff is responsible for defining the QA program, writing the QA program description for safety analysis reports, and writing and publishing the QA manual. Through its audit program, the corporate headquarters staff is also responsible for evaluation of architect-engineer and other support group QA programs. The QA field staff at each plant Lg gi managed by a QA site manager who reportstothevicepresident7 through the QA manager. The QA site manager provides an independent review and evaluation of the adequacy and effectiveness of the site QA program. He ensures that field activities in-volved in construction, preoperational testing, and plant operations conform to QA program requirements and approved procedures. The Q^. program -is fully describcd in wcticr.17h h G4 b uM g Will oc4. grodda kdund sopped (,45 NIMed W 8ec. ben 15.1.IDI een. s,% 1.x>) (or % op-hoa o 4-k elad-vode-. A l dwks op%_ e4 o,,mba Ji\\ 6. t dd 4 val ty i aHore bucMous, whch a (o I discrihed. so sethon 17. 2. i

VEGP-ESAR-13 TABLS 13.1.1-1 (3HEET 1 OF 26) OFFSITE TECHNICAL SUPPORT Richard J. Kelly, executive vice president-power supply Responsibility and Authority overall responsibility for the design, engineering, construction, and operation of all company generating facilities and fuel procurement Educational Background Georgia Institute of Technology B.S., electrical engineering -Professional Experience and Training Georgia Power Company Draftsman, designer, distribution engineer, design engineer, generating plant electrical engineer, chief 4 electrical engineer, chief engineer, manager of production, general manager of production, vice president and general manager power generation, senior vice president-power generation, and senior vice president-group executive-power supply Involved in the design of electrical underground transmission and distribution systems; assigned electrical design duties and responsibilities for hydroelectrical plants on the Georgia Power Company. system, the duties of which included the design of two new hydroelectrical generation stations constructed on the system during the years 1957 to 1963 as well as major electrical modifications to several existing hydroelectric stations Involved in all electrical phases of thermal steam plant design since 1959, including 14 fossil steam units put into operation since that time as well as three units presently under design and construction; also involved in the two nuclear units now in operation and two units in the design and construction stage Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 2 OF 26') George F. Head, senior vice president-power generation Responsibility and Authority Responsible to the executive vice president-power supply for the safe, reliable, and efficient operation and maintenance of all generating plants (May 1981-present) Educational Background Georgia Institute of Technology B.S., mechanical engineering Professional Experience and Training Georgia Power Company Senior vice pres'ident-power generation, general office power generation, May 1981 Vice president and general manager-fossil and hydro generation, general office power generation, January 1980 4 General manager-fossil and hydro generation, general office power generation, November 1979 Deputy general manager-power generation, general office power generation, January 1978 i Deputy general manager-production, general office production, May 1977 Manager-production, ger.eral office production, August 1975 Assistant. manager-production, general office production, February 1973 Superintendent-prcduction, general office production, July 1969 Coordinator of engineering and construction for Plant Hatch, September 1968 Production engineer, general office production, July 1968 Assistant superintendent, Plant McDonough/Atkinson Amend. 4 2/84

VEGP-ESAR-13 TABLE 13.1.1-1 (SHEET 3 OF 26) Production engineer, general office production, August 1964 Southern Services, January 1964 Southern Services representative at Enrico Fermi Nuclear Plant for 6 years Assigned APDA and PRDC, April 1958 Plant test engineer, Plant Yates, March 1956 Assistant plant test engineer, Plant Hammond, March 1955 Richard E. Conway, senior vice president-engineering, construction, and project manager Responsibility and Authority Overall responsibility for the direction and delegation ot 4 responsibility to the engineering, construction, a td project management organizations to ensure that t! sir designated functions are accomplished in an efficient and timely manner (1981-present) Educational Background Georgia Institute of Technology B.S., mechanical engineering Harvard Business School 78th advanced management program Professional Experience and Training Southern Company Services and Georgia Power Company, Birmingham, Alabama Vice president, 1978-1981 Georgia Power Company Project general manager, Scherer Project, 1976-1978 Superintendent of generating plant construction, 1969-1976 Project superintendent, Plant Hatch, 1968-1969 Amend. 4 2/84

7 VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 4 OF 26) Assistant project superintendent, Plant Branch, 1967-1968 Engineering-construction department, 1963-1967 Assistant plant test engineer, Plant Yates, 1961-1963 Paul D. Rice, general manager-quality assurance and radiological health safety Educational Background Vanderbilt University B.S., mechanical engineering Protessional Experience and Training Georgia Power Company /U.S. Navy Commenced nuclear career in 1957 in the Navy nuclear program; held various management positions in the program 4 including 10 years in the senior oversight position at major private and Navy sites where naval reactor plants wne constructed and overhauled; has 21 years experience in the nuclear field Jesse T.

Beckham, Jr.,

vice president and general manager-nuclear generation Educational Background Georgia Institute of Technology B.S., chemical engineering Professional ~ engineer, mechanical engineering Professional Experience and Training Georgia Power Company Responsible for the safe and reliable operation of the operating nuclear units; responsible for directing the operation of the units, providing the licensing support, and providing the corporate guidance and control for these units; during the construction phase at VEGP, responsible for ensuring that the necessary procedures Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 5 OF 26) and startup activities are progressing, along with providing the initial qualified operating staff'for the plant Prior to present assignment, held positions throughout the state while working for Georgia Power Company, including approximately 5 years at Plant Hatch during startup and also 2 years at Plant Branch U.S. Army Captain prior to joining Georgia Power Company in August 1963: served in the U.S. Chemical Corps Jack C. Causey, vice president-fossil and hydro generation Responsibility and Authority Responsible for the management of all of the fossil and 4 hydro generating plants Educational Background Georgia Institute of Technology B.S., electrical engineering Professional Experience and Training Georgia Power Company (past 5 years) Manager-power generation Manager-power generation services Robert H. Bohler, manager-power generation services Responsibility and Authority 4 Responsible for directing a staff of approximately 50 employees in providing technical field and support services to the company's power generating plants (August 1979-present) Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 6 of 26) Educational Background Georgia Institute of Technology B.S., electrical engineering Georgia Power Company Nuclear reactor engineering course, 1958-1959 Professional Experience and Training Georgia Power Company Assistance chief electrical engineer, June 1976-August 1979 Chief-engineering services, November 1972-June 1976 Scheduling and standards engineer, April 1971-November 1972 Distribution substation engineer, July 1970-April 1971 4 Customer substation engineer, June 1968-July 1970 Senior design engineer, June 1956-June 1968 Senior draftsman / design engineer, December 1949-June 1956 Emsley F. Cobb, manager-nuclear planning and control Responsibility and Authority Responsible for management of the activities of the nuclear planning and control department in providing support services to the company's nuclear plants in the areas of planning, budget controls, procurement, security, and materials mar.agement (May 1981-present) Chairman-safety review board, October 1980-June 1982 Educational Background Auburn University B.S., electrical engineering Amend. 4 2/84

e VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 7 OF 26)- Professional Experience and Training Georgia Power Company Assistant to senior vice president and group executive-power supply, May 1978-May 1981 Responsible for providing assistance to the senior vice president and group executive-power supply U.S. Navy Positions in the fossil propulsion plants of several fossil surface ships and assigned to various positions in three nuclear submarines, including commanding officer; provided direct nuclear training to eight nuclear submarines and coordination of nuclear repair efforts in the same submarines from the position of deputy squadron commander, having direct responsibility for these eight submarines, December 1955-December 1958 and October 4 1961-May 1978 Additional Training Simulator training, Sequoyah Nuclear Plant Senior reactor operator Pressurized water reactor orientation Max Manry, manager-nuclear performance Responsibility and Authority Responsible'for the management of activities of the nuclear performance department in providing nuclear plant support in the area of nuclear performance (April 1983-present) Educational Background Auburn University B.S., mechanical engineering Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 8 OF 26) Professional Experience and Training Georgia Power Company Plant manager, VEGP (pressurized water reactor), April 1982-April 1983 Plant manager, Plant Hatch (boiling water reactor),- maintained senior reactor operator license, April 1978-April 1982 Assistant plant manager, Plant Hatch, maintained senior reactor operator license, January 1976-April 1978 Assistant plant superintendent, Plant Hatch, January 1971-January 1976 Assistant plant superintendent, Plant McDonough-Atkinson (fossil), July 1969-January 1971 Plant results engineer, Plant McDonough-Atkinson, May 4 1967-July 1969 Plant results engineer, Plant McManus, August 1963-April 1967 Plant test engineer, Plant Yates, June 1962-August 1963 Assistant plant test engineer, Plant McManus, August 1960-June 1962 Assistant plant test engineer, Plant Arkwrie:ht, January 1960-February 1960 Additional Training Radiological monitoring Introduction to nuclear power Basic nuclear fundamentals Boiling water reactor technology Observation training Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 9 OF 26) Simulator training Balance of plant Prelicensing course (Plant Hatch) John J. Badgett, manager-nuclear training Responsibility and Authority Responsible for all company nuclear training (May 1983-present) Educational Background U.S. Naval Academy B.S. degree Professicnal Experience and Training Georgia Power Company Superintendent-training, VEGP (senior reactor operator license certified) General Physics Corporation Pressurized water reactor simulator instructor, 1980-1981 U.S. Navy Senior 2aspector for the 57 naval technical training commands (inspection and quality assurance), 1978-1980 Manager of a major submarine training center, 1975-1978 Executive assistant to the commander of a flotilla, (approximately 30 nuclear-powered submarines), 1974 Commanded a nuclear submarine tender (maintenance, repair, and logistics support activity), 1972-1974 Directed and supervised the training of five nuclear-powered attack submarines (operational training and readiness certification), 1971 Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 10 OF 26) Commanded two nuclear-powered fleet ballistic missile submarines, 1966-1970 Additional Training Advanced management and reactor supervisor and safeguards training, Office of Naval Reactors, Washington, D.C., 1966 Advanced training strategic weapons and ballistic missile systems, naval guided missile school, Dam Neck, Virginia, 1965 Naval nuclear propulsion program training, naval nuclear power school, Bainbridge, Maryland, 1964 N; val nuclear power plant operational training, DIG prototype, West Milton, New York, 1964 Len T. Gucwa, manager-nuclear engineering and chief nuclear 4 engineer Responsibility and Authority Manages the nuclear engineering division of Georgia Power Company's power generation department involving nuclear engineering, nuclear fuel, and nuclear reactor regulation (July 1983-present) Educational Background University of Tennessee B.S., nuclear engineering Georgia Institute of Technology M.S., nuclear engineering Georgia State University M.B.A Professional engineer, State of Georgia Certified senior reactor operator Amend. 4 2/84 m

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 11 OF 26) Professional Experience and Training Georgia Power Company Since January 1971 in the engineering, regulatory, and operational support of Georgia Power Company's nuclear reactors, including reactor safety, radiological, and nuclear fuel cycle activities; in July 1983 named manager-nuclear engineering and chief nuclear engineer Raymond D. Baker, nuclear regulatory engineering manager Responsibility and Authority Responsible for licensing of Plant Hatch Educational Background University of Tennessee 4 B.S., nuclear engineering Professional Experience and Training Georgia Power Company Engineer and then manager in the nuclear engineering division, nuclear generation department, July 1979-present Engineer in nuclear section of the engineering department, later the power supply engineering and services department, VEGP, August 1972-July 1979 Engineer-in-training in engineering, production, and construccion departments, January 1972-August 1972 William E. Burns, nuclear engineering and evaluation manager Responsibility and Authority Responsibilities centered around licensing in the areas of long term retrofit and generic regulatory issues, fire protection, security / safeguards, special engineering activities, inservice inspection, and decommissioning Amend. 4 2/84

i VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 12 OF 26) Educational Background Georgia Institute of Technology B.S., mechanical engineering Professional Experience and Training Georgia Power Company Worked in the nuclear engineering division of the power generation. department and power supply and engineering services department in positions from design engineer to nuclear engineering and evaluation manager, 1976-present U.S. Navy Lead engineering officer of the watch and staff production; training assistant at the S5G naval nuclear propulsion power plant prototype 4 Engineering division officer onboard an 55W nuclear-powered submarine, 1971-1973 Steven C. Ewald, manager-nuclear chemistry and health physics Responsibility and Authority Responsible for nuclear facility emergency preparedness programs, environmental monitoring programs, and support of site health physics and chemistry programs Educational Background Macalester College B.A., physics with minor in mathematics and education 1, Michigan State University M.S.,. physics with research in nuclear physics Michigan State University M.S., mechanical engineering with emphasis on analysis, modeling, and optimization systems Amend. 4 2/84 va

f VEGP-FSAR-13 j TABLE 13.1.1-1 (SHEET 13 OF 26) Professional Experience and Training Georgia Power Company Manager-nuclear chemistry and health physics, July 1983-present Power generation engineer, October 1981-July 1983 Supervisor-nuclear training, VEGP, June 1960-October 1981 U.S. Nuclear Regulatory Commission, Region II Radiation specialist, January 1977-June 1980 Michigan State University Nuclear reactor supervisor, division of engineering research, August 1973-January 1977 4 Charles T. Moore, nuclear operations analysis manager Responsibility and Authority Responsibilities include plant support in areas of nuclear plant operations analysis, licensee report review, generic review, safety evaluation program, and accident analysis Educational Background Georgia Institute of Technology B.S., industrial engineering Professional engineer, mechanical, State of Georgia Professional engineer, mechanical, State of Alabama Senior reactor operator license certified, Plant Hatch Professional Experience and Training Georgia' Power Company Muclear operations analysis manager, June 1983-present Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 14 OF 26) Assistant plant manager on loan to the Institute of Nuclear Power Operation, Jun'e 1981-June 1983 Assistant plant manager, April 1979-May 1981 Power generation engineer, February 1977-March 1979 Assistant production engineer, September 1975-January 1977 Test engineer, February 1974-August 1975 Assistant plant test engineer, August 1972-January 1974 Engineer-in-training, September 1969-November 1969 U.S. Air Force Officer in charge, aerospace systems branch, August 1970-July 1972 4 Maintenance officers course, February 1970-August 1970 Charles W. Hodges, power generation manager III Responsibility and Authority Responsible for the management of Plants Arkwright, Hammond, McDonough/Atkinson, and Yates (fossil) Educational Background Auburn University B.S., mechanical engineering Professional Experience and Training Georgia Power Company Plant manager, Plant Scherer (fossil), past 5 years U.S. Navy 1951-1955 Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 15 OF 26) Carl L. Donaldson, Jr., manager-power generation Responsibility and Authority Execute direct supervision of plant managers and responsibility for their compliance with company policies for the most efficient operation and maintenance of generating facilities under his supervision (July 1979-present) Educational Background Georgia Institute of Technology B.S., electrical engineering Nuclear reactor engineering course, 1958-1959 Professional Experience and Training Georgia Power Company 4 Manager-production services, May 1977-July 1979 Assistant to senior vice president-power supply, June 1976-May 1977 Assistant chief electrical engineer, November 1972-June 1976 Chief-engineering services, January 1971-November 1972 Methods engineer, September 1969-January 1971 Electrical equipment engineer, January 1968-September 1969 Senior design engineer, July 1963-January 1968 Design engineer, June 1961-Ju' 1963 Junior engineer, December 195*, ' 1961 Preston S.

Nix, Jr., manager-power gen 4 tion Educational Background Howard College B.S.,

engineering physics Amend. 4 2/84 L

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 16 OF 26) Professional Experience and Training Georgia Power Company Manager-power generation, October 1982-present Plant manager, Plant Bowen, November 1976-October 1982 Plant manager, Plant Hammond, June 1972-November 1976 Assistant plant superintendent, Plant Yates, August 1969-June 1972 Assistant test engineer, test engineer, and results engineer, Plant McManus, July 1962-August 1969 David W. Howell, supervisor-power generation technical services Responsibility and Authority 4 Areas of cesponsibility include power generation procedures, training, power systems, environment, water conditioning, computer application, system performance, and fire protection (August 1979-present) Educational Background Rose Polytechnic Institute B.S., mechanical engineering Professional Experience and Training Georgia Power Company Assistant plant manager, Plant Hammond, July 1978-August 1979 Assistant to senior vice president-power supply, July 1977-July 1978 Procedure engineer, January 1976-July 1977 Results engineer, Plant Wansley, July 1975-January 1976 Results engineer, Plant Branch, July 1973-July 1975 Amend. 4 2/84 i

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 17 OF 26) Assistant test engineer, Plant McManus, October 1970-July 1973 U.S. Army Signal Corps R. H. Taylor, senior fire protection specialist Responsibility and Authority Developed and established a departmental fire prevention / fire protection program for the company's 31 generating plants and coal transloading facility Educational Background West Georgia College B.A., psychology 4 B.A., sociology Professional Experience and Training Georgia Power Company Supervisor-skills development center, 1974-1975 Safety engineer (safety and fire protection program), Plant Hatch, 1971-1974 Plant operator, Plants Tallulah (hydro), Burton (hydro), Sinclair (hydro), and Yates (fossil), 1960-1971 David M. Ratclif'fe,. general manager-fuel services department Responsibility and Authority Responsible for management of fossil fuel supplies for Georgia Power Company, including procurement and administration of coal and associated transportation contracts Educational Background Valdosta State College B.S., biology Amend. 4 2/84

I VEGP-FSAR-13 TABLE 13.1.1-1 (SHEFT 18 OF 26) Woodrow Wilson College of Law Juris doctorate State bar, Georgia Professional Experience and Training Georgia Power Company Manager-fuel services, fuel services department, 1979-1981 General supervisor-production laboratories, power generation department, 1976-1979 Supervisor-fuel and environmental functions, power generation department, 1976 Senior biologist, power generation department, 1974-1976 Biologist, power generation department, 1971-1974 4 .Raymond C. Ashe, fuel contracts manager Responsibility and Authority Responsible for providing Georgia Power Company's input into development, reviews, and execution of new contracts and contract amendments; completes federal reports on fuel usage; reviews and administers purchases; adjusts contracts for calorific values; and supports procedure drafting and corporate planning activities Educational Background Georgia Institute of Technology B.S., electrical engineering Emory University Juris doctorate State bar, Georgia Professional Experience and Training Georgia Power Company Manager-fuel supply, fuel supply department, 1970-1979 Assistant to vice president-electric operations, 1963-1970 Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 19 OF 26) Division meter superintendent, 1960-1963 Meter laboratory supervisor, 1954-1960 Distribution engineer, 1947-1954 Daniel N. MacLemore, Jr., vice president and chief engineer-power supply engineering and services Educational Background Georgia Institute of Technology B.S., civil engineering Professional Experience and Training Georgia Power Company 4 Directs the power supply engineering and services organization in providing the company with engineering management, technical support, and engineering design services for operating hydro, fo'ssil, and nuclear generating plants, transmission lines, and other facilities; ensures adherence to applicable operating requirements, improves the efficiency of operations, and reduces cost for plants under construction; 1983-present Project general manager-hydroelectric projects, 1978-1983 Chief civ._ and mechanical engineer, prior to 1978 Kenneth M. Gillespie, manager-engineering services Responsibility and Authority Responsible for managing engineering services division of power supply engineering services (December 1981-present) Educational Background Clemson University B.S., mechanical engineering Amend. 4 2/84

m-- VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 20 OF 26) Professional Experience and Training Georgia Power Company Construction project manager, VEGP, July 1978-December 1981 Project superintendent (construction project manager), Plant Hatch, October 1974-July 1978 Assistant project superintendent, Plant Hatch, July 1973-August 1974 Onsite mechanical engineer, Plant Hatch, July 1969-July 1973 Mobile nuclear exhibit manager, Atlanta, June 1968-July 4 1969 Results engineer, Plant Hammond, March 1967-June 1968 Test engineer, Plant Hammond, February 1964-March 1967 Assistant plant engineer, Plant Arkwright, June 1961-June 1962 U.S. Army January 1962-February 1964 Additional Training Management techniques EEOC training Productivity seminar Nuclear power at nuclear utility services Clovis R. Thrasher, Jr., manager-engineering Responsibility and Authority Manages civil engineering division, mechanical engineering division, and electrical division (1978-present) Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 21 0F 26) Educational Bac' ground Massachusetts Institute of Technology Civil engineering diploma Ge rgia Institute of Technology B.S.. civil engineering Professional engineer (civil) Professional Experience and Training Georgia Power Company Chief civil engineer, civil and mechanical engineering department, 1976-1978 Civil engineer, civil and mechanical engineering 4 department, 1967-1976 Structural engineer, engineering department, 1964-1967 Design engineer and structural engineer, engineering department, 1956-1964 Designer and design engineer, engineering department, 1952-1956 Senior draftsman and designer, engineering department, 1948-1952 T. E. Byerley, manager-environmental affairs Responsibility,and Authority Responsible for environmental reports for construction permits and operating licenses for Plant Hatch and VEGP; supervises nonradiological environmental monitoring Educational Background Georgia Institute of Technology B.S., mechanical engineering Amend. 4 2/84

VEGP-ESAR-13 TABLE 13.1.1-1 (SHEET 22 OF 26) Professional Experience and Training Georgia Power Company Manager-environmental affairs, June 1976-present Assistant to chief civil and mechanical engineer, 1969-1973 Positions in design construction of fossil fueled steam generating plants and hydroelectric plants, 1941-1973 Additional Training Nuclear power Nuclear fuel workshop Introduction to nuclear power 4 1971 Westinghouse school for environmental management Boiling water reactor - simulator training general physics, Chattanooga Boiling water reactor - systems, Plant Hatch Curtis P. Stinespring, III, project manager-engineering services Responsibility and Authority Secures all engineering services for a fossil plant, combustion turbine plant, and a barge / train coal transloader; manages engineering, budget, end scheduling for major retrofit construction projects; manages engineering in cupport of construction, power generation, and project general manager for nuclear plant under construction (January 1982-present) Educational Background Georgia Institute of Technology B.S., civil engineering Amend. 4 2/84

m VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 23 OF 26) Professional Experience and Training Georgia Power Company Project manager-engineering services, February 1978-January 1982 Structural engineer, civil and mechanice.1 engineering department, November 1973-February 1978 Assistant structural engineer, July 1972-November 1973 Senior. design engineer, July 1971-July 1972 Design engineer, July 1968-July 1971 Junior engineer, June 1967 Junior engineer, North District sales, April 1967-4 June 1967 Junior engineer, South District sales, February 1967-April 1967 Junior engineer, Atlanta Division Underground, September 1964-January 1965 U.S. Army Signal Corps, January 1963-January 1967 Harry G. Maheras, chief generating plant electrical engineer Responsibility and Authority Responsible for the management of the overall operation of-the generating plants electrical engineering department (March 1981-present) Educational' Background North Carolina State University B.S., electrical engineering Amend. 4 2/84

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 24 OF 26) Professional Experience and Training Georgia Power Company Project manager-power supply engineering and services department, April 1978-February 1981 Generating plant electrical engineer, electrical engineering department, April 1976-March 1978 Senior test engineer, senior protection engineer, and section head, system operations department, June 1969-March 1976 Junior engineer, test engineer, and senior test engineer, systems operations department, January 1966-August 1969 Engineer-in-training, employee relations department, June 1965-December 1965 4 William C. Philips, chief mechanical engineer Responsibility and Authority Responsible for engineering support for all operating plants, plants under construction, and technical support for utility committees (EEI, AEIC, and EPRI); provides evaluation of alternate energy sources and research and development programs; responsible for evaluation of the piping contractor quality control and quality assurance _ programs at VEGP (January 1983-present) Educational Background University of Florida B.S., mechanical engineering Professional Experience and Training Georgia Power Company t Assistant project section supervisor (construction), Plant Scherer, September 1976-January 1983 Assistant project section supervisor (startup), Plant j. Wansley, October 1975-September 1976 'I I Amend. 4 2/84 n .he

VEGP-ESAR-13 TABLE 13.1.1-1 (SilEET 25 OF 26) Junior engineer, associate engineer, and construction engineer, Plant Bowen, December 1971-August 1975 Major Henry Thompson, Jr., chief civil engineer Responsibility and Authority Responsible for the civil planning, architectural, hydraulic, structural, and materials section (January 1978-present) Educational Background Georgia Institute of Technology B.S., mechanical engineering Professional engineer (civil) 4 Professional Experience and Training Georgia Power Company Hydraulic engineer, January 1970-January 1978 Senior design engineer, design engineer, and junior engineer, June 1962-January 1970 Ronald H. Pinson, vice president and general manager-generating plant construction Responsibility and Authority Directs construction and modification of generating plant facilities; provides technic'al guidance for field construction activities; maintains relations with contractors, labor unions, and governmental agencies; coordinates interdepartmental working relationships; and provides for development of departmental personnel (July 1981-present) Educational Background Auburn University B.S., mechanical engineering Amend. 4 2/84

3 VEGP-ESAR-13 TABLE 13.1.1-1 (SHEET 26 OF 26) Professional E.xperience and Training Georgia Power Company Vice president and general manager-generating plant construction, July 1981-present Ceneral manager-generating plant construction, January 1980-July 1981 Project general manager, Scherer Project, November 1978-January 1980 Manager-generating plant construction, October 1976-November 1978 4 Assistant superintendent-generating plant construction, October 1971-October 1976 Plant superintendent, Plant Bowen, June 1970-October 1971 Plant superintendent, Plant Yates, July 1969-June 1970 Assistant plant superintendent, Plant Yates, August 1964-July 1969 Plant results engineer, Plant Mitchell, June 1963-August 1964 Plant test engineer, Plant Hammond, February 1961-June 1963 Assistant plant test engineer, Plant Hammond, January 1959-February 1961 0363V Amend. 4 2/84

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VEGP-FSAR-13 13.1.2 CPERATING ORGANIZATION 13.1.2.'1 Plant Organization The VEGP consists of two nearly identical nuclear generating units. The plant organization applicable when both units are operational is shown in figure 13.1.2-1._ The plant staff, excluding the security department,gw111 ce manned with approximately StS full-time employees. Y6k 13.1.2.2 Plant Personnel Responsibilities and Authorities 13.1.2.2.1 Overall Plant Management The heeng ecaese. V,bje %t. Camb MVMd 3p--. m2 nager t e VEGP is responsible for direct management of the plant, including industrial relations, -planning, coordination, direction of operation, training, maintenance, refueling, and technical activities. The -pl:nt-64AVUD - n ;:r is responsible for compliance with the requirements of the operating license,Inthegggggg3..pecifications, and quality tech the Mana$ ntofbi.] nager'

absence, assurance program.

c_____ The p opwqk3pg 22:ict;nt pl:nt ;;n;;;r assumes this responsibility. GmveJD mamesprr will designate in writing other qualified personnel to assume overall plant responsibility in his absence. (See paragraph 13.1.2.2.2 for succession of responsibility for overall-plant operation.) Q AA V A)b O edm> the [,cO"ma _ ac._ ports to the manager-nuclear 5 c---*4 ^n in The p 3..;t ;; nag;_r e epartment. The manager-nuclear g report ectly to the g g president and general 94A manager-nuclear-, n. The p_____ ..:n;;;- has access to the advice and services of~ technical specialists within Georgia i Power Company (GPC) and outside expertise as necessary. Reporting to the,fquvM O_ nt ;;n;;;r directly and indirectly are the following selected positions: th, w u sit. o#- Vni4-O rwmba.s A. An :::ict;nt plant ;; nag:r, who, along with the pkant CSAVdd j manager, is-responsible for the overall operation and maintenance of the plant. B. The superintendent-operations, who is responsible for operating the plant safely and efficiently. C. The superintendent-plant engineering and services, who is responsible for onsite engineering and technical support of the plant. j 13.1.2-1

E VEGP-FSAR-13 D. The superintendent-maintenance, who is responsible for performance of preventive maintenance and repairs on plant equipment. E. The health physics superintendent, who is responsible for the radiation protection program of the plant. F. The superintendent-regulatory compliance, who is responsible for advising plant management on matters concerning compliance with the Final Safety Analysis Report (FSAR), operating license, technical specifications, approved plant procedures, emergency plan, security plan, etc., and other applicable fede ral', state, and local regulations. G. The quality control supervisor, who is responsible for performance of work inspections,_ verification of procedures used in the control of special processes, 4 % Svpwm b L 4 o+qnt control of the plant.9csee*<4 and material equipm Togo k &o g C a pk W H. The superintendent-administration, who is responsible for. developing and implementing office practices which enable correspondence and other general office activities to be accomplished _ efficiently. I. The superintendent-nuclear training, who is responsible for the development and implementation of the training ~and retraining programs for the plant staff. The superintendent-nuclear training is also responsible for administering use of-the training simulator. J. The materials supervisor, who is responsible for preparing requisitions for.all operational spare . parts, equipment, and miscellaneous supplies for plant use.. The materials supervisor is also responsible for receiving, inspecting, shipping, storing,-and maintaining an inventory of spare parts equipment and supplies. The. work experience and educational background requirements for department heads and selected personnel are described in subsection 13.1.3. ~i h m o % o,. g g. g 7 g g p. g g 1 M NtDEb tu T ABl.E. n.1 Z_ --h 13.1.2.2.2 Operations Supervision and Shift Organization The' superintendent-operations is responsible to plant F management for-the operation of the two units of VEGP and shall possess a senior operators license. The superintendent-operations communicates closely with the other plant / I 13.1.2-2 i

VEGP-FSAR-13 superintendents and supervisors with regard to activities at VEGP. The(supervisor \\ operations) reports to the superintendent-npa ra t-i nn s, The . supervisor-operations shall possess a senior operators license. The N.Et ch E E.?:N is responsible for seeing that plant operations are conducted in accordance with appropriate standing orders, plan g g t(n g;;rgcedures, and technical specifications. The e..... supe.

r s principal responsibility is ensuring safe plant operation during his l

assigned shift as addg g g q th g quirements of item I.A.1.2 of.NUREG-0737. The c..... up:P7f;cr shall possess a senior operators license. ombd sop w Under the supervision of th_e chift su-- v;pz. s c r, the shift supunnsee shall assist the d1W N % Wf E 7 with his duties and

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responsibilities and shall possess a senior operators license. In addition, he keeps a record of all shift activities and establishes unit load as directed by the load dispate er y as 0%rWsor 3 emery g coyg g ons dictate. Reporting to the shift 3 o r _ _ _ _ _ _ _jrc=2.1 are the plant operators, assistant pIant operators, and plant equipment operators. Theshifttechnicaladvisorreportstothesh64thifprvi'sor during emergencies and acts to provide both perspective in assessment of plant conditions and dedication to the safety of the plant. -During normal operations, the shift technical l7 advisor will report to the senior shift technical advisor, who reports to the superintendent-operations. The shift technical l3 advisor position meets the intent of NUREG-0660, as clarified by NUREG-0737, item I.A.1.1. The shift technical advisor sition may be eliminated if the qualifications of the -hif;81 rVlsor are upgraded. Section 13.2 describes shift technical advisor training, and subsection 13.1.3 describes shift technical advisor qualifications. Assistant plant operators monitor the status and make adjustments as needed to maintain control of the various plant processes. Most of their duties are confined to the control room, although they perform routine inspections in other areas of the plant. The operating crew may make radiation and containment surveys within the plant. (In addition to the control room personnel, a health physics technician is on duty during plant operations.) The Technical Specifications state l3 the shift manning requirements for all modes of operation. The succession to responsibility for overall operation of the

plant and the authority to issue standing or special orders, in Amend. 3 1/84 13.1.2-3 Amend. 7 5/84

1 VEGP-FSAR-13 the event of absences, incapacitation of personnel, or other emergencies, shall be as follows: l:nt man:;er. GeonaAL. M444uR. %gMe. Wdene Oyudou s @LWMb) ' A. B. Assistant plant manager. MuawA UUL %4 io o3 C. Superintendent-operations. D. Senior reactor operator-licensed superintendent as designated by the plant ::n:ger. G4AV kDb E. Operations supervisor. F. Shift supervisor. n ewift 5 r--on 13.1.2.2.3 Engineering, Health Physics, Laboratory, and Maintenance Supervision The superintendent-plant engineering and services reports to an n

i m ut plant.aenagee and supervises the engineering staff.

gg y - Reporting to him are the plant ~ engineering supervisors and a fire protection specialist. (See subsection 9.5.1 for description of Open4 o% fire protection program. )- i The functions of his staff are to monitor-plant performance, provide technical support for plant operation, provide writing support, and interface with other groups to ensure proper engineering support for plant operations. The plant engineering supervisors report to the superintendent-plant engineering and services and aid in his duties and responsibilities. The plant engineering supervisors normally determine when to call consultants and contractors for dealing with complex problems beyond the scone of_the company's staff. This position, therefore, corresponds closely to that identi'fied.as " engineer in charge" by ANSI 18.1-1971. wo cteMT*f W ma om4-De* mi The. health physics superintendent reports to n.rgp;; tant p @. nt= 3 p --- ;-r:and is responsible for the radiation protection program. He verifies that waste shipments or releases of radioactivity from the plant comply with federal, state, and local regulations. Also he ensures that appropriate monitoring derices and protective. clothing are available. He is . responsible for radiation monitoring devices used by personnel entering the plant and for the maintenance of all required radiation exposure records of plant support and visiting personnel. 13.1.2-4

VEGP-FSAR-13 The laboratory supervisor-health physics is responsible to the superintendent-health physics and will aid the superintendent with his duties. 4(ktms7af The laboratory supervisor-chemistry wor. ug(gr the direction of the superintendent-health physics /fn 14 r6sponsible for performing chemical, radiochemical, and radiation sample analyses and maintaining the plant makeup water demineralizer to ensure proper water quality. Laboratory personnel advise operations staff on the operation of plant systems to maintain water quality within the specified limits. The superintendent-maintenance directs and plans maintenance activities with the assistance of other departments. He has reporting to him maintenance supervisorg and instrumentation and controls supervisors. Maintenance supervisors and foremen direct electricians and mechanics in the upkeep of equipment. Instrumentation and controls supervisors and_ foreman are responsible for directing technicians in testing, calibration, surveillance checks, and repair of plant instrumentation and control systems. 13.1.2.2.4 Quality Assurance and Quality Supervision QMVMD The-p.;nt manager is responsible for the development and implementation of the quality assurance program during the initial test phase and operational phase of VEGP. Reporting to $vp(n;kgkf%he pl:nt

nager, the quality control supervisor will be g, (yI assurance program.spection activities required by the quality responsible for in q

DMfanu QICL Pet TheAgeneralt manager-quality assurance and r:di^'m"4 cal haa++h and --#a*y, as described in section 17.2 of the FSAR, is responsible to the executive vice president for managing L activities of the GPC quality assurance organization. The quality assurance organization will provide a comprehensive independent audit of safety-related activities to verify that they are in compliance with the quality assurance program. The quality assurance program during operations is discussed in section 17.2. M N 6.\\.l. L 5 S 13.1.2.3 Operating Shift Crews A total manpower in excess of five full shift crews is provided arei..-~.. to avoid excessive overtime. T- : m wico, c. - - - -.. 1 1 ---eina vonniv.---*e e-a

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Insert 13.1.2.2.5 13.1.2.2.5 PRE 0PERATIONAL AND STARTUP ORGANIZATION The Initial Test Program Manager .The Initial Test Program Manager reports to the General Manager Vogtle Nuclear Operation.. The Initial Test Program Manager is responsible for development and direction of The Initial Test Program Policies and Procedures. that are necessary to ensure a successful test program. The Startup Manual describes The Initial Test Program Organization, defines the responsibilities of involved organizations and personnel, delineate personnel ~ qualification and contains the n cessary admini trativ control

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[ TLt.sb h of- %.preee O alad.5 ovq u ao (6 S REPORTING TO THE INITIAL TEST PROGRAM MANA ER DIRECTLY AND INDIRECTLY ARE THE FOLLOWING SELECTED POSITIONS: -::.:. n A. The Scheduling and Planning Superintendent is responsible for the development and maintenance of Initial Test Program schedules and .of scoping information. The Scheduling and Planning Superintendent reports to the Initial Test Program Manager. B. The Schedule Supervisor is responsible for the development and update of schedules required to support the Initial Test Program. The Schedule Supervisor reports' to the. Scheduling and Planning Superintendent. The positions reporting to the Schedule Supervisor -will be schedulers assigned to Start-Up, both GPC and contract. The Schedule Supervisor will provide direction to the schedulers in the performance of their duties. C. The Scoping Supervisor is responsible for the development and ~ maintenance of system scoping /subscoping information to the support system turnover. -The Scoping Supervisor reports to the Scheduling and Planning Superintendent. The Scoping Supervisor provides guidance as to scoping philosophy and technical assistance to the Test Supervisors. D. The Construction Acceptance Test Superintendent is responsible for the development and implementation of the-CAT program. The CAT Superintendent reports to the Initial Test - Program Manager. The CAT Superintendent represents a single point of contact for all L phases of the CAT program. He will utilize primarily maintenance personnel to complete CAT testing. r;

p i E. The Construction Acceptance Test Supervisor is responsible for ensuring that CAT.'s are completed in a timely manner to support the Start-Up Summary Schedule. The three (3) CAT Supervisors have responsibility divided according .to discipline. The disciplines are electrical, mechanical, and I & C. The 1 CAT Supervisors report to the - CAT Superintendent. Support for completing CAT's primarily is from maintenance personnel. The CAT Supervisors will provide work orders and schedule information l to maintenance personnel to complete the individual CAT's. F. The Preoperation Test Superintendent is responsible for development and implementation of preoperational testing policies and procedures that are necessary for a timely completion of the Initial Test Program.

The.Preoperational Test-Superintendent reports to the Initial Test 1

Program Manager. The positions reporting to the Preoperational Test Superintendent represent a matrix-type organization composed of Lead Test Supervisors. l Test Supervisors, Procedures Supervisor, and Special Test Supervisor. Additional ' support personnel will' be reporting to the Preoperational . Test Superintendent to supplement the operating staff during peak . work periods, ( The Special Test Supervisor is responsible for conducting assigned tests and for directing the individuals providing support for the test activities. The Special. Test Supervisor reports. to the Preoperational Test Superintendent. This position will be supported by plant personnel, L contractors, or other Southern system employees in completing assignments. ~ i l G. The Procedure ' Supervisor Eis responsible for the development ofi and L adherence to procedure preparation schedules and administrative requirements. The Procedures Supervisor reports to the Preoperationel-Test Superintendent. l No positions report to the Procedures Supervisor. The ' Procedures-Supervisor will, however, coordinate ~ with the Construction Acceptance Test Superintendent, Preoperational Test Superintendent and the Hot l-Functional and Start-Up Superintendent to develop the required procedure L preparation schedules and to maintain the current status of procedures preparation. H... Technical support will provide assistance to the Lead Test Supervisor and/or the Test Supervisors Lin their testing activities and ' assist. l. in the development of preoperational test procedures. t Technical Support' personnel-report to the Preoperational Test

Superintendent.

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i 1 I. The Lead Test Supervisor is responsible for ensuring timely . implementation of preoperational-phase testing.and turnover activities - so as to. support initial test program objectives and milestones. The Lead Test Supervisor reports to the Preoperational Test Superintendent. The positions reporting to the Lead Test Supervisor represent a matrix-type organization composed of test supervisors. The lead Test Supervisor provides specific technical assistance and direction to the test ~ supervisors in conjunction with turnover and testing activities. The Lead Test Supervisor provides the initial review of the completed preoperational test procedures. !J. The Test: Supervisor is responsible for conduct of system turnover-and testing activities to support the initial test program objectives and milestones. The Test Supervisor reports to the Lead Test Supervisor. K. The Hot Functional and Start-Up Test Superintendent is responsible for directing - the activities associated with flushing, energization, hot' functional testing and start-up testing. This position reports to the Initial Test Program Manager. The positions _reperting' to the Hot Functional and Start-Up Test Superintendent are the Energization Supervisor, Start-Up Test Supervisor,-Hot Functional Test Supervisor, and Flushing Supervisor. L. Start-Up Test Supervisor, and Hot Functional. Test Supervisor are responsible for conducting the assigned tests and: for directing the individuals providing support for the test activities. - These positions report to the Hot Functional and - Start-Up _ Test-Superintendent.. They will be supported by plant personnel, contractors. - or other Southern system employees in completing their assignments. M. The. Flushing Supervisor 'is responsible to the Hot Functional and Start-Up Test Superintendent for the development ' and implementation-of. the flushing procedures and to coordinate the. implementation. of - the flushing procedures in order to verify plant systems -are cleaned ~ to the cleanness level specified. The' Flushing Supervisorareportsi to the Hot Functional' and' Start-Up . Test Superintendent. The positions reporting to the - Flushing Supervisor represent a matrix-type organization. Test Supervisors will report to the Flushing Supervisor while ' their. assigned systems are being flushed.. Also,' reporting _ to 'him will be flushing support such as plant : operations . personnel, laboratory personnel,- and flushing support crafts.from Construction. 1 y v i >--t-er-- 1_-g-wee,'sm-- e e c ye rpy-as.--e9---3g--.-er,.-g-,se,,gy,----t:yga-- =rwf,.,=,ey*,---p..,v--~--a. r-"se,y.swi-m er-- e w-w%W y---- --M-+

~... i -N.- The Energization Supervisor is responsible for energization of the plant electrical distribution in a safe and timely manner as needed to' support the initial test program objectives and milestones. The Energization Supervisor reports to the Hot Functional and Start-Up Test Superintendent. The ' Energization Supervisor coordinates electrical system Construction Acceptance Tests and Preoperational Tests to support the initial test program, to minimize the use of temporary power, and to minimize power disruptions of the plant electrical distribution. -13.1.2.2.5.1 QUALIFICATION OF PREOPERATIONAL AND STARTUP PERSONNEL Initial Test Program Manager and Program Superintendents Individuals' performing these functions shall meet the following requirements: -(1.) A Bachelor Degree in Engineering or related science. (2.) Four years experience in responsible _ positions related to power generation of which three years shall be nuclear power. Lead Test Supervisors, and Preop and Startup Program Supervisors Individuals ' performing any 'of these functions shall have, as a minimum, and Bachelors degree in Engineering or related science and three years . of - power. plant experience -including two. years Nuclear Power Plant experience. CAT and: Flush Program Supervisors Individuals who perform this.. function shall meet-the following. Preop -Phaseminimum requirements: ( 1.-) A High School Diploma (2. ) ' Four-years - experience _ in the: craft or discipline he supervises, o'ne year of which shall be Nuclear Power Plant experience. LTestSupervisor..(PreopPhase) Individuals performing as. Test Supervisors during the Preop Phase shall -satisfy the following minimum requirement: -(1.) Bachelor Degree in Engineering or related science. (2.) One (1) year of power plant experience. . (3. ). Engineering Technology. (Systems).. Training (or equivalent). (4.) ' Start-Up Program Procedures (SUM)l Training (or equivalent).

? ly. T Test Supervisor (Start-Up Phase) -Individuals perfonning as Test Supervisors during the Start-Up Phase shall satisfy the following minimum requirements: (1.) Bachelor Degree in Engineering or related science. (2.) Two (2) years of power plant experience of which one (1) year shall . be nuclear power plant experience. =(3.). Engineering Technology (Systems) Training (or equivalent). (4.) Start-Up Program Procedures (SUM) Training (or equivalent). 13.1.2.2.5.1.1 g, p[;; SPECIAL CONSIDERATIONS Individuals who do not possess the. formal education requirements specified s in'this procedure shall not be automatically eliminated where other factors providg sufficient demonstration of their abilities. The Initial Test Program Manager shall evaluate these persons on a case by case basis and-provide documentation-of this evaluation in the qualification. record. Guidance contained in referenced documents may be used in this evaluation. S Completion of formal education beyond the requirements may be used 'by ithe Initial Test. Program Manager as partial satisfaction of experience requirements. V . N% (, a s 4 h

L VEGP-ESAR-13 During' refueling operations, when the reactor core configuration is being altered, a senior reactor operator will supervise the fuel handling activities in the reactor containment. Licensed operating personnel will be trained in the radiation protection procedures and will be capable of performing routine or-special radiation surveys using portable radiation detectors. These operators will be trained in the use of . protective-barriers and. signs, protective clothing and . breathing apparatus, performance of contamination surveys, and checks on radiation monitors. Plant personnel will be trained .'in the limits of exposure rates and accumulated dose. The shift supervisor is responsible for implementing the radiation . protection program in the absence of the superintendent-health physics orchis designated alternate. k b 6 I3 - }. )'1 ANd F.sf}R Ques i3, 2.1-1 " d I3'L 2 - 2Ck k Sc.b h h L ~ ),m.__.L s ko. m t vo;.. h a M i M h e inimo n A,4 s.k{4,q Q g p +* 0364V - 13.1~. 2 - 6 Amend. 3' 1/84

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E E N N O O I T [ E E I H H A 8 E E N N IL I i j L O ,5 R E f E i S S ,SmI im V ,a,P R E U S i] l, y RO CI s S .R t i w. V a E 1 P m U S EC ' [N i g= gl T N RO t S I I n V mI R a >P S U l -s j j ,m u, I a m J C 1 e t T22 rV a a m A a r 2 1. r 1 o 1 s r N3 s A 2 1 GR T E ORE i] jj UE s H TGIS e N a s A .s F i i L nn i u n iS P =r i = f M a H C ] y=j C !mS m a ,.V 5 = PU la H / ar w" 5 N I J H V PO t t J, 2 2 7, 4 n y R / w =5 1 ,a a', i l, s g, = = s v e a a i ] .O R I ,S / imI m L 1 V R 1 a,S i. E PU E T ], J S E i T O C R mI m m ,S 7 F V t. E R E t aS i a PU

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o

~ =

5 P

gag = 30 gt: 5 3 =a e-vh w & _r a -a -ar O d La E a a y l I l I = a 2 g o 5 t-sg 4 ~a* g EE 55 UR gE 35 3 1: 2; a=s ,= ge as se

== 2 E "" 2$ 5$ h$ R a. l I I l 1

I 35

!EE 535 535 "5 EE:&il a s& ER "x -- l I I l W

s t A +a.a .s A e. e a- +=s pa-J a + - +.a = s e ,,esn m.-.a A n. r O 6 g ( b W

ES 0%

oW '*\\i E. 50?ETV 15(Ry MR $0N O E L J 1 i e i d E hg. i f + 4 W f r

TABLE 6. g, 2 -3 MINIMUM SHIFT CREW COMPOSITION

TWO UNITS WITH A COMMON CONTROL ROOM UNIT 1 IN MODES 1,2,3, OR 4 UNIT 2 IN MODE:

POSITION 1,2,3, OR 4 5OR6 DEFUELED OS 1 1 1 SRO 1 1 1 RO 3 3 2 NLO 3 3 2 STA' 1 1 1 UNIT 1IN MODE 5 OR 6 UNIT 2 IN MODE: ~ POSITION 1, 2,3, OR 4 5OR6 DEFUELED 08 1 1 1 SRO 1 0 0 RO 3 2 1 NLO 3 3 1 STA* 1 0 0 UNIT 1 DEFUELED UNIT 2 IN MODE: POSITION 1,2,3, OR 4 5 OR 6 DEFUELED OS 1 1 0 SRO 1 0 0 RO 2 '1 0 NLO 2 1 0 STA' 1 0 0 , men, THE STA IS NOT REQUIRED ON SHIFT IF THE QUALIFICATIONS ' OF THE OPERATIONS SUPERVISOR ARE UPGRADED TO FULFILL THE REQUIREMENTS OF THE STA POSITION. !l

VEGP-FSAR-13 113.1.3 QUALIFICATIONS OF PERSONNEL -13.1.3.1 Qualifications Requirements American National Standards Institute (ANSI) N18.1-1971, -Standard for Selection'and Training for Nuclear Power Plants, is currently used-as a basis for establishing the qualifications for personnel-in the plant organization. ' Personnel will~either meet the minimum education and experience recommendations of ANSI 18.1-1971 or will complete a , qualification program which will demonstrate their ability to perform their job functions. -Table 13.1.3-1 with designated ANSI N18.1 equivalent titles, states the requirements for work experience and educational

background for key plant personnel.

The following definitions will be used'for qualification of personnel. 13.1.3.2' Definitions Nuclear power plant - A nuclear power plant is'any plant using a nuclear reactor to produce electric power, process steam, or space-heating. Experience - Experience is. actual applicable _ working experience in design, construction, startup,-operation, maintenance, or technical services. Academic training - Academic training is successfully completed. college. level work leading to a recognized degree. Related technical training - Related technical training is formal training beyond the high school level in technical subjects associated with the position in question, acquired in training schools or programs conducted by the military, . industry, utilities, universities, vocational schools, or others. On-the-job. training - On-the-job training is participation in nuet. ear power. plant etartup, ' operation, maintenance, or -tecnnical' services under the direction of appropriately experienced personnel. 13.1.3-1

VEGP-FSAR-13 13.1.3.3 Qualification of Plant Personnel Nuclear power plant experience will be that nuclear experience acquired in-the design, construction, startup, or operation of nuclear power _ plants. Further, nuclear experience acquired at military, nonstationary, or propulsion nuclear plants may qualify as equivalent experience on a one-for-one time basis. Nuclear experience acquired in nonpower plants such as test, research, or production reactors may qualify as equivalent to nuclear power plant experience on a one-for-one time basis. Training may qualify as experience if acquired in appropriate reactor simulator training programs on the basis of 1 month's training being equivalent to.3 month's experience. Training programs, the culmination of which involves actual reactor operation, may qualify as equivalent to nuclear power plant experience on a one-for-one time basis. On-the-job training may qualify as equtvalent to nuclear. power - plant experience on a one-for-one time basis. The qualification of the initial staff personnel holding key managerial and supervisory positions as described in paragraph 13.1.2.2 1 are provided in table 13.1.3-1. 4' u 13.1.3-2 Jy

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t - e s r e r ae r f o e e p v o r p tn t-l u sa S e n p e e s P s e e ae v y e s e f i-de e. d s r ee c o r s n r C M e e s p e s, s e s y e c y s nes r a w-I e h e n n i a r e a o V n ei _e i n v L e e e o p tg e s ^ a n e t C n t r-i tr 6 ne e .t ene t s t t e n a e s rn a t r a e e a e p s d t r a rr t e e t 88 t ee r r e ne C a s e r es n s e t k a t b 3 e a n .e.- pg pa e e L t p G t 8 a .r p e m ap e es s ke e kt o s e D t t (e *~ r gn e 6r g a s e n e, e. g e d s a s, e e n u n tt m e r - 4n, t er re o g a e r e ue. ce e r n e l t g g nr e t g .o o n e a o s t r ia es n sG e e e, a g t s n e s s a r e s e e a a t t, g , p m m nC e s ee e m e e s t s s dh. ee se se n e ts a t I a n it 6c eg n s g rs es e e e a e e m a s s re t n. e ct e

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l, VEGP-FSAR-13 c.p 13.2 TRAINING i

m 13.2.1 LICENSED OPERATOR TRAINING The VEGP licensed staff will consist of individuals with significant differences in pre'.io^us education, training, and experience.. The licensed training programs have been j formulated to provide the required training based upon the

i. individual's prior experience.

These programs are designed to I-provide the highest degree of operator proficiency by l effectively using the VEGP simulator. i. l- .13.2.1.1 Training Programs The details of typical training programs, including syllabus, i -duration, classroom, and on-the-job training, are contained in b tables 13.2.1-1 through 13.2.1-5. The programs described in l these tables will remain the same for both units before and i after initial. fuel loading. I-f .L - .W J/ r.9 Jc 0 -J i (j_ 9 Of M.e 5 W J'r' nA J p) L x x 3. % ; e y a l s } ..y p,aZ: ' ,V.e. w am A m l l*5. 2. i -l l3.E.l ( &r 4)) /JMs*/*/ n. f c. bfyy//A24 - }yr 'b l f 0. rTs ^./.E }/) JA4.H i

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i I These programs are designed to train personnel with various i backgrounds as indicated in the above tables. These tables include position, titles, and experience of the individual. The VEGP training department is responsible for the coordination of teaching courses and supeivising the instruction. The VEGP training department is shown in figure e 13.2.1-1. The qualifications of instructors and a description l, of the instructor requalification program'are found in j paragraph 13.2.1.3.3. I

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r, /S. 'L. /. /. 2. VEGi Ey w nc/ $<.oud</x (/t c:u->~ p/d N, osse 6.d /E5 /* [y% % d,0 w o A w a u as.ub.id k /c c;g rr.c / e b.dd&/ a dA e."2. i -i Ww& v /3.%./-f. 4.ic,w w s' /eekidS a L- /. 2. t. t. B VE=G /# p &l& k&/m rc e L i< - s J Tich>y/d b y+Kw e,wy & /4 iocarr abd ;~&p ad%Zd a 7A '3. 2.i-' Wd. '2. 2. i - 1 as s Y Y N . l. ls I 8 4/ 6,GGA>dd Cas,ig,d df 4 y s dm a457is a / v 9.< w d y % g 4 n /o w rs e W d'

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Ah y ' Y J CU g -W /Yk0 /2 f) j l/3.~2.././.& l 5 aN LC %'.:/ C ' Training for mitigating core damage will have the course ' content as described in NUREG-0737, item II.B.4, and will. be jjtaught during the cc.urses scheduled in the syllabus, as shown ,in tables 13.2.1-1 through 13.2.1-5. I l. } e. 2.. i. i., &6aasse&, ndDaALdm+ Zaag i l /f y 5,- ( Y A4Af~ / Y,c1r id~ l f a a <s a l'5 < c m s 4 % s-~6-a %6 4 aw wks AJ % av )sau.+;u,wo/c p s,k. LTLo w&q ! W u e n A L ~ 0 p s=j=g rny

/sh.w.c ypo As v6

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QA1l A YJ44!~l SWNr / *(MU j ts.>psAlN/ Yn w /, j* 2J e.- sp?,, nd Jy V g ' VecR /3. 3. / /. 8 f6.:. 6 n / AYa d Y cl d Y 'J t.ts b $ Y C* 5 W ,4/?.6/. YfjA cacA' tw&ukf. Aur<> avMuzi ?$,ewa , n 'Ahbhh>llJ dAA. d Lt U L &,//^$sp7% y

Ypwa, 6,..

y& Cimwp'yn xf& fi,,a.< wid 6 wafi<a&/' 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 VEGP simulator examination. Since applications for license must be made before the audit examination results are usually available, Georgia Power Company (GPC) will certify to the extensive operating experience based upon the individual's satisfactory progress in the training program. If the individual fails to demonstrate the ability to pass an audit examination or the l3 ability to~ properly manipulate VEGP simulator controls, GPC 'will request that the NRC not administer an examination to this individual. Occasionally, the audit examination may uncover a ( hd f li'

u~ t VEGP-FSAR-13 weak area in an individualfs knowledge, but if GPC believes that the individual has suffi& tent time to correct the problem, certification will not be withdrawn. 7/egarchart[:h-Rinfigure[13.2.1-2-d '-M show3 he t schedule of the licensed operator training program in ielation to the schedule for preoperational tests, fuel load, criticality, and the expected time for license examinations. If fuel loading is significantly delayed, the VECP license requalification program will be used to maintain operator proficiency. 13.2.1.2 Operation Experience 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-l water reactors.

The cold license training program will also contain a program of 10 reactor startups on a research/ tost type reactor to gain actual "at the controls" experience. Personnel gwith prior Navy nuclear experience as an engineering watch 10 officer, engineering watch supervisor, reactor operator, or other equivalent positions or those who have prior commercial . nuclear plant licensed operator experience shall be exempted lfrom 10' reactor startup requirements. A combination of the l preceding will satisfy the experience requirements of !NUREG-0737, items I.A.2.1. The details of the simulator program

are contained in tables 13.2.1-1 through 13.2.1-5.

c.; C,7 A ri__'_-' 4+h nay1=+ y n"4da 1 149 ui+k M.d', f= u =2..i u.. m... % 7 h~ V EC e A nwD i J A c.o ~ A L /2ep w M i. m )% dns i<>< & 4&pk D, p/q y p s i g,. n a 'k%. fu Avdg w.& rLpn y, A&R i-Dy' un,m &y ') NAM nc/ m a6i i wmm ,a p.+ s h C. e v & <l b tb.4 k b % pr6 ~ ~ 4 4 d: ^ r. M ) Y v' l @ cA w y o+Ed w/4 J C G s.

rv i 8 I Through_the.use of startup test data, operator observationg cu;;??ted E; pl--t - 5 _7 t

' >\\

l and plant change notices, the VEGP simulator will be modified and tested to match plant response. 13.2.1.3 Qualification and Requalification Program The qualification and requalification program for licensed operators and the training department is described in the following paragraphs. i t l 1 e s k i h I L_

y i l l. VEGP-FSAR-13 -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 13.2.1-5. 13.2.1.3.2 Licensed Operator Requalification Program f ,,N d' fa,

lh yu J (),

k d u w, % d u d & 3 D. _M y ,y if iaauma Gn ep&g 1%~a - M 4 46M1< m & pn sj n n L m a m 'd sf - a W ~g & qu,/ oa v ns l .o M sve 4 w' A 7J >%gn nuak n. age: M g fecab E Wu A - [ ~p/dl l& mad u,4 dm Jh f,amAd d< w 't a a 4 A Wip ZQ;4& Qm/h/ h h wh a mm y a 4 w 4 t<

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q. 7,w p gy.

yn-y la f f S I

7., l l N 13.2.'l.3.2.1 Classroom Study. A planned lecture series will be presented annually (i.e., each calendar year). covering those 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. J. Quality assurance for operations. K. Major upcoming events. L. Heat' transfer, fluid flow, and thermodynamics. h Y& FAuV M F/wwA uc~ps gs at C & y Q & w-8 9,4 u % p eww Re4 M k.JLC' 4 I

F L l, i. M. Mitigation of accideftte involving a degraded core.- f5 l nM M b cra M l /;M :~ k ~r e i r.9 o-AM A %g i X Su y 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, reactor shutdowns, or other control manipulations t l. I I!'l' l' I

VEGP-FSAR-13 ( 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 (t performed on the VEGP simulator. The followi-ng control manipulations and plant ,g,4 evolutions are acceptable for meeting the. reactivity control manipulations required by Appendix A, g F Paragraph 3.a., of 10 CFR 55. The starred items shall be performed on an annual basis ave--d 15 ;;..C. jg '-~*

a all other items shall be performed on a 2-year cycle 10 g__.

m

_____2 ,,-_mt.. Con <.e Tie 7eadni yekrs). 41. P 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 j feedwater during startup and shutdown. ( 4. Boration and/or dilution during power operation.

5.

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

6.

Loss of coolant including: Significant pressurized water reactor (PWR) a. 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 core coolant flow / natural circulation. ( 10. Loss of condenser vacuum. f 13.2.1-4 Amend. 10 9/84 r. -:- - - ~. :-- u-- "~ ~

T'0 m mm, - VEGP-FSAR-13 11. Loss of service water. 12. Loss of shutdown cooling. ( 13. Leas of component cooling system or cooling to an individual component. L r i I C V' 13.2.1-4a Amend. 10 9/84 wo- - . K k. L in ~ :, :..;r s

f. ^ - - - VEGP-ESAR-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. 23. (.- Malfunction of reactor coolant pressure / volume control system. 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, ( assistant plant manager, or plant manager. An unsatisfactory result on the evaluation shall require 13.2.1-5 = * .a % l,. p

1 c.1 ~. T VEGP-FSAR-13 r 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 participation in operation of the plant or the VEGP simulator. C. Plant Chang'es Each licensed operator will be kept informed of all k plant design changes, procedure changes, and license changes. Changes of a magnitude requiring detailed , explanation will be reviewed by a special lecture with 100 percent attendance of licenced personnel. D. Procedures Each licensed operator will review abnormal and emergency procedures at a minimum of once each 12 months. A delinquency of 30 days on a procedure review will require that the licensee be removed from license 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, assistant plant manager, plant manager, and certified 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 operator from required attendance at requalification i 13.2.1-6

*. i.$d A :..O.m ci.egp_.f__

VEGP-FSAR-13 N 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 wri,tten 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. h ht.< <0 $0 sy7t A< ma p'o.a. A%ud 4n - Jif 4 f af>AT ~44 . 9 >% spp &9 =~ m w6 m e ~ ><E J J >%6 w,ancy~ w 4 k e r' s t % ~ ac Q *iGJ &7 <oe f.! d !M. O i l

e Lr* - C. Lecture Examinations 5 Written examinations will be given to individuals who 'y e received less than 80 percent on the pertinent section .v" (/= of the annual examination covering material presented ' 1 JM. in the progranriteture series.

A grade of less than

';80 percent on any required lecture series ex 4 < T 'r F amination ahall require a licensed operator to be rescheduled j?c for additional instruction and testing on that subject 'within the next 3 months. The 3 months may be extended by the length of time of any refueling outage falling within that period. Lectures presented for information of major upcoming events and/or plant godifications may be' documented by attendance record. ,o 13. 2.1.'3'. 3 Instructor Qualification and Requalification Program N, 1The' qualification and requalification program for instructors as' described below includes requirements of NUREG-0737, item i I. A.~ 2'. 3 lt ,/ b' W / l r< i k 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' qualification checklists shall include the following requirements: ag I-i 4 6 e .,,,,,...,.,,,,,,,.,,,.m,_#,,,,, ,,.,,m,.._..,7,,._,., .h,,.y,, _,, ,,,,_,,,.v. -,---r_,,,=,.<.%, e--

y. r~1 i VEGP-FSAR-13 1. The instructor's supervisor will review the employee's background and establish qualification . goals and qualification'5eadlines. Besides other qualifications, the following minimum goals will be established: For new instructors who do not have a l a. classroom teaching background, the employee will' have to present a lecture to a group cf experienced instructors before lecturing plant students. The company's instructor course as a minimum shall satisfy this requirement. b. For instructors who teach licensed students, before the new instructor conducts a comprehensive program, the employee will meet NRC requirements by obtaining the appropriate . certification. This requirement does not prevent noncertified members of the training staff from teaching licensed personnel in the instructor's area of expertise. 2. The superintendent-nuclear training shall approve the qualification checklist at the time of issue and shall approve the final qualification of each instructor. Before these instructors teach integrated response, transients, and simulaf.or courses to licensed operators, they will demonstrate their competence by , successful completion of a senior reactor operator examination. b B. Certified Instructor Requalification Licensed or certified instructors will complete the requirements of the licensed operator requalification i program annually by teaching, performing, or taking examinations for each required element of the requalification program. Conducting simulator training will be considered the same as supervising license duties _in the plant control-room. If an instructor is not involved in the preceding requalification program, he may renew his ( certification by preparing for and taking or l . conducting a comprehensive audit examination. Instructors who fail to complete these annual instructor requalification requirements,will not teach 6 1 l' L

y ;- - = =: VEGP-FSAR-13 integrated plant response to licensed students until they renew their certification. i I ( i I l 1 \\ \\ s' (- .- 0366V 13.2.1-9 Amend. 7 5/84 -.~ : w &_L.a_,,_ a. -.,

T* VEGP-FSAR-13 TABLE 13.2.1-1 (SHEQ1 OF 3) LICENSED OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH COMMERCIAL PWR LICENSE OR NRC CERTIFICATION h0 (ANY SUPERVISOR 4 STAFF O" Or 1 M POSITION) g oR t Minimum Description h Integral Duration Nuclear power plant theory Classroom or /# Fundamental of reactor theory self-study General core design Radiological safety and radiation hasards Heat transfer, fluid flow, and thermodynamics Fluids and matter Fluid Statics Fluid dynamics Heat transfer by conduction, 4 convection and radiation Change of phase - Boiling Bv.rnout and flow instability Reactor Heat transfer limits VEGP systems and procedures Classroom or / A Procedures for design and self-study operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications i Reactor safety systems Emergency and reserve systems Containment and shielding i Radiation monitoring system Auxiliary systems Radioactive waste i-I t I- !i h I! i. i

? 91 VEGP-FSAR-13 1 TABLE 13.2.1-M Sheet 2 of 3) ? Minimum l-Description h Integral Duration } VEGP license and technical Classroom or 1 week g specifications self-study License conditions and k limitations Design limitations I Puel handling and core Classroom or 3 days alternations self-study Facilities and procedures Classroom Simulator 4 ) Control Room Operations Neeks h g General operating X X (including characteristics VEGP/ainulator) Specific operating X X characteristics Load changes X X Operating limitations I X Standard, emergency, and X X plant procedures Control manipulation X Transients X Mitigating core damage Classroom or 1 day Incore instrumentation self-study Excore Instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation Observation training including VEGP 3 months (a) walkthrough training (only for personnel who have not previously held a same type lic'ense, reactor operator or senior. reactor operator)

fdb VEGP-PSAR-13 TABLE 13.2.1-1 (Sheet 3 of 3) Minimus Description M Integral Duration p Walkthrough training VEGP 3 weeks (only for personnel who have previously held a PWR SRO b license) l Review and audit

1. week t

4 a. Prior to initial criticality, applicants for cold licenses will . complete observation training at a' comparable licensed commercial

nuclear power plant for a period of 6 weeks.

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

y I VEGP-FSAR-13 TABLE 13.2.1-2 MHEET 1 OF 3) ggy LICENSED OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH OTHER THAN PWR LICENSE OR NRC CERTIFICATION STAFF N POSITION) (ANY SUPERVISOR 4 4 I OR l t Minimum Description g Integral Duration Nuclear power plant theory Classroom or Fundamental of reactor theory self-study / Ok General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and thermodynamics Fluids and matter Fluid Statics Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase - Boiling Burnout and' flow instability Reactor Heat transfer limits VEGP systems and procedures Classroom or Mw Procedures for design and talf-study operating changes 4 Reactor coolant system mechanical design Reactivity control mechanisms and indications' Reactor safety systems Emergency and reserve systems 4 Containment and shielding . Radiation monitoring system Auxiliary systems Radioactive waste 'I w-I

Y)7 1 l VEG?-FSAR-13 2. TABLE 13.2.1-j'(Sheet 2of3) Minimum Description Tjgte Integral Duration VEGP license and technical Classroom or 1 week specifications self-study License conditions and I limitations Design limitations b Fuel handling and core Classroom or 3 days alternations self-study Facilities and procedures Classroom Simulator t Control Room Operations 5 weeks General operating X X (including 100 A characteristics VEGP/ simulator) Specific operating X X characteristics Load changes X X Operating limitations X X Standard, emergency, and X X plant procedures Control manipulation X Transients X Mitigating core damage Classroom or i day Incore instrumentation self-study Excore Instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation Observation training including VEGP 3 months (a) walkthrough training {r-1-7 fe. r.... __. 1.;.. ;.... C. 7.;1d ; :--- 2

-- ': ;1 nae t;;: 11....,....;;;;;

ar---* r :: ;;..i;; ;;;;;d:*. ~ r;::;;;:)q; 1 1 .,,,e

(# VEGP-FSAR-13 TABLE 13.2.1-1 (Sheet 3 of 3) Minimum Description Tyyjt Integral Duration "- 1 s. k.-...k 4 4-- -(,, .ugen (1, _3... t _ qs, g laa'r # r p_....... 1 -uv h.v. s 7:rrirc:17 '-l'

ri. !"^

( I 11;; :;) ",. b Review and audit I week .I i a. Prior to initial criticality, applicants for cold licenses will complete observation training at a comparable licensed commercial nuclear power plant for a period of 6 weeks. In addition, applicants will have at least 6 weeka of VEGP shift experience which. includes walkthrough training.

VEGP-FSAR-13 TABLE 13.2.1-3 (Sheet 1 of 3) LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS PERSONNEL WITH I YEAR i 1 0F MILITARY PWR EXPERIENCE AS A REACTOR OPERATOR ENGINEERING WATCH I SUPERVISOR, OR ENGINEERING WATCH OFFICER (ANY SUPERVISOR OR STAFF ~ j POSITION) f Minimum I k. Description Tjgte Integral Duration Nuclear power plant theory Classroom or 3 weeks I' Fundamental of reactor theory self-study General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and t thermodynamics Fluids and matter Fluid Statics j Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase - Boiling Burnout and flow instabilf.ty Reactor Heat trvnofer limits 4 VEGP systems and procedures Classroco or 4 weeks Procedures for design and self-study operating changes Reactor coolant system mechanical design Reactivity control. mechanisms 'and indications Reactor safety systems Emergency and reserve systems Containment and shielding Radiation monitoring system j Auxiliary systems l Radioactive waste e f E 4 i l L Il. w 4 4 n,,.,,.. - - ,--w-- g-ge.,m.-- w

w.,.y,,,

.,,,m, ,.m e e., ,wm.n,- -,ss- ~,,,,,w,,, ,,,+-,, _..,,. _. .._,c, a n

l VEGP-FSAR-13 i TABLE 13.2.1-3 (Sheet 2 of 3) Minimum Description g Integral Duration j VEGP license and technical ~ Classroom or 1 week ~g specifications self-study License conditions and k limitations j Design limitations 1 i Fuel handling and core Classroom or 3~ days alternations self-study Facilities and procedures ) Classroom Simulator i Control Room Operations 5 weeks i General operating X X (including 100 h characteristics VEGP/ simul ator) Specific operating X X characteristics Load changes X X Operating limitations X X Standard, emergency, and I X plant procedures Control manipulation X Transients X Mitigating core damage Classroom or 1 day Incore instrumentation self-study Excore Instrumentation Vital instrumentation Primary chemistry Kadiation monitoring Gas generation Observation training including VEGP 3 months (a) walkthrough training _ tan 1y en, p...--mmi ohn h...A .rt pr-=*4nni=1y held a amma o '"7^ 110' 22, 7:220 ! e;---t r e- -- ' r..;;;;; i 0;OrITT) k

Ts2 l [ VECP-FSAR-13 3 TABLE 13.2.1-f(Sheet 3of3) Minimum Description M Integral Duration I

u. u.. s.. s., 4,,4,,. ;

ocom _2 m.. m g g & ly I:: ;;;;;..h! k p;;:1:2:17 '-if - ** **^ 9 1 lier ::} Review and audit I week t i I Prior'to initial criticality, applicants for cold licenses will a. complete observation training at a comparable licensed commercial nuclear power plant for a period of 6 weeks. In addition, applicants will have at least 6 weeks of VEGP shift experience which. includes walkthrough training.

f.,,

1 1 l j + VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 1 OF 3) smeg v LICENSED OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH DEGREE IN ENGINEERING OR APPLICABLE SCIENCES STAFF OR n"E"J.T^".* POSITION) (ANY SUPERVISOR 4 g ok e 1 i Minimum Description h Intearal Duration ggh Nuclear power plant theory Classroom or Fundamental of reactor theory self-study General core design Radiological safety and radiation hazards Heat transfer, fluid flow, and thermodynamics Fluids and matter Fluid Statics . Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase - Boiling Burnout and flow instability Reactor Heat transfer limits 4gh VEGP systems and procedures Classroom or Procedures for design and self-study operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications Reactor safety systems l Bnergency and reserve systems 2 ~ Containment and shielding 'l Radiation monitoring system [ _ Auxiliary systems Radioactive wasta l' i -. I

VEGP-FSAR-13 4 TABLE 13.2.1-MSheet2of3) Mini===n Description T ge Integral Duration Z i. VEGP license and technical Classroom or 1 week specifications self-study License conditions and b limitations Design 1Laitations i Fuel handling and core Classroom or 3 days alternations self-study Facilities and procedures Classroom Simulator i Control Room Operations 5 weeks General operating X X (including 100 h characteristics VEGP/ simulator) Specific operating X X characteristics Load changes X X Operating limitations X X Standard, emergency, and X X plant procedures Control manipulation X Transients X Mitigating core damage Classroom or i day Incore instrumentation self-study Excore Instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation Observation training including VEGP 3 months (a) walkthrough training -{::17 ':: p;.....

'. -t.: ':- : ',

r.:: ;;;;i:x;17 h:1' - ---- '.

,7 11...,

O 2; !;;;Z vs asuAus s.-=;..

p:!;t;!)

y e VEGP-FSAR-13 TABLE 13.2.1 L(Sheet 3 of 3) Minimum Description Tjgan Integral Duration 1- 'Jeli;t;;;;h :::' *-- 4 4 "- k" % (;;17 f e; p;;:::: 1 r5r '-"- 4, pr e.. er--17 k.1a. nun enn 9 h lic;;;;' i. g Review and audit I week l t n' a. Prior to initial criticality, applicants for cold licenses will complete observation training at a comparable licensed commercial ~ nuclear power plant for a period of 6 weeks. In addition, applicants will have at least 6 weeks of VEGP shif t experience which. includes walkthrough training.

y av e VEGP-FSAR-13 TABLE 13.2.-1-54 SHEET 1 OF 2) LICENSED OPERATOR ONSITE TRAINING SYLLABUS (PLANT OPERATOR OR ASSISTANT PLANT OPERATOR) l Minimum Description Type Integral Duration class com g)r l10 Nuclear power plant 12 weeks 5 "I - theory Mathematics Fundamentals of reactor theory General core design Reactor and health physics and radio-logical safety-Materials Heat transfer, fluid ficw, and thermodynamics Fluids and matter Fluid Statics Fluid dynamics Heat transfer by conduction, convection and radiation Change of phase - Boiling Burnout and flow instability Reactor Heat transfer limits t-i i: VEGP systems for / 2 Oh electrical and reactor control Classroom or (including self-study procedures) Reactor coolant system mechani-cat design Reactivity control mechanisms and indicators Reactor safety systems Emergency and reserve systems Containment shielding Radiation monitoring systems Auxiliary systems t

f98 VEGP-FSAR-13 TABLE 13.2.1-5-4 SHEET 2 OF 2) Minimum Description Type Integral Duration Classroom Simulator (o Control Room Operations fweeks General operating X X (including 100 h characteristics VEGP/ simulator) 4 e - t r <,.,,7 - g <. g A x y s..m....______ m Load changes X X Operating limitations X X

Standard, mergency, and X

X plant procedures Control manipulation X Transients X Mitigating core damage Classroom or 1 day Incore instrumentation self-study Excore Instrumentation Vital instrumentation Primary chemistry Radiation monitoring Gas generation Observation training including VEGP 3 months (a) walkthrough training I. ~ Review and audit I week Prior 'to initial criticality, applicants for cold licenses will a.complete observation training at a comparable licensed commercial nuclear power plant for a period of 6 weeks. In addition, applicants will have at least 6 weeks of VEGP shif t experience which. includes walkthrough training.

- (..-. i. 4 PLANT MANAGER MANAGER NUCLEAR TRAINING ~ N I ._____.____.__J SUPERINTENDENT NUCLEAR TRAINING ORAFTSMAN CLERK -l l f SUPERVISOR SMULATOR OPERATIONS MOOlFICATION TRAIN 8NG SUPERVISOR j. SIMULATOR - SIMULATOR PLANT INSTRUMENT ENG8MEER _ INSMUCTOR ENGINEER TECNNICIAN 'o*H 3-a \\ fd#81VL'O #- k j -f SuPERv SOR - i r+9)cf &ltTw pg,,, TN.Ae4:4 TRAIN 1000 J \\ I_ L F ~ {gcu o A. e ETtroo 5 j TRANNNG SENIOR MEMOOS ,g7 ' /*uo 7 A AiMid C METNOoS ANo g, g pg(gg g.7 SPEC' '.sST-A"8 7"""""8 t SPEC AuST C j. tEGEse9 1 SRO -Senternesseeropereier

Methode and treenme specishete wm have empenence in electricot er mechnical meanwnence, inarwnensessen and controle technetegy, or health physics and chemistry.

Leorgialbwer A U, T A T. FIGURE 13.2.1-1 . 4m*.. ..2.

W l h' h l UdF 4 A 7. s 'g ~~ J' F s, m o 41 4t a 1 .4 a b 3g hD CS l' y 5 is 5a A o o S y a} g. i c. w + + A ty M.w. q' s bEi_ Leno twoo Carncau,y umir i 2 ,1 o d D 0 0 c-co w, b Y h k 30 -V l? h\\ h gk hE ~ ~ ~ PR.coPt12AmovAe lesrwc, Unir 2 [ Litef:g CyAm 2 'Em 1 ( Geovr. S y,

)

o .o a:l Y7 W .I ~~ g3 3 c N g Ltceusc EVA UN m I ( Gecui: Ij ra g e v ,a o O A (f' g$ g *s eo 'o U fr o I" e a Pteciennouni_ Test unir i i g c) N U o C' e oo { t-ao 00 c-5 gp e h c3 $ 3 hO El d t ( O FSM suemcrTAt 'E I a -+; f,g m v m 45 7 v 3 -3 O O o g y f N d r Q tA a j k 'A;, b~ G i .L g i N, i. e d 7 .Jf O ~3 dl i 4 o, i i ~% k )4

9

$;kej 0 2 2 n a ~w 1~

$b l D f .p. 4 MONTHS TO FUEL LOAD 54 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 Requalification Pre-License Fuel Load Training operational Exams and Starts Tests Unit 1* Criticality i f ~ j C+Td Ei Oy' e tions Technology (20S) (6M) -:zi7a Shi' echn 1Adv r( i l Licensed rators (12S) (6M) (6M) l to Support t Tests ~(! -6 Nonlicen dpeIntors (12S) (6M) to Su gr ratioopiTests Licensed Supervisors (20S) (15M) 2 to Su F lLoad j to Support uel Load (12S) (6ka) Licensed rYors i Nonlicensed Operators ( S* *) (9M) l to Support Fuel Load I Legend l " ~ ' ~ " " " 5 l M = Minimum staffing plans l S = Students who start training GPC expects to license over 50 individuals for fuelload with a 5 minimum of 27 required to operate VEGP Unit 1. O, I

*
Depends upon turnover.

~ st$cinec ommenATimo rs.4mr 1 Georg. Pbwer ia omri ano unir w D. FIGURE 13.2.1-2 l dat t e

f' D D D D D MONTHS TO FUEL LOAD 51 48 45 42 39 36 23 30 27 24 21 18 15 12 9 6 3 Preoperational License FuelLoad Tests Exams and Unit 2' Criticality o Licensed Operators (12S) (6M) to Support Pre perati nalT sts Nonlicensed Operato to Support Preoperation ests (S* *) (6M) I Licensed Supervisors (78) (6M) to Support Fuel Load / ~ Licensed O rators to Support elLoad (12S) (6M) 2 Legend M = Minimum staffing plans S = Students who start training For the operation of Unit 2, GPC expects to license a minimum of 18 additional individuals. Licensed individuals will have a dual license for both Units 1 and 2. Depends upon turnover. ADDITIONAL VEGP UNIT 2 vocTLE ELECTRIC GENERATING PLANT OPERATIONS TRAINING GeorgiaIbwer omr uNo omr FIGURE 13.2.1-3 433-9 e

f.2 d i. L VEGP-FSAR-13 13.2.2 TRAINING FOR NONLICENSED PLANT STAFF The VEGP staff will consist of h dividuals with significant ~ differences in previous education, training, and experience. The training programs have been formulated to provide the required training based upon the individual's prior experience. Personnel will either meet the minimum education and experience recommendation of ANSI 18.1-1971 or complete a qualification program /ANS perform the specific tasks.which will demonstrate their ability to gj p g k YAMt 'I k @

p

\\\\ ad, >&g a, M//# ymm 'lbb ) lo w / n Y/*ff Nk DN n gp

a. 2. / -/.

I. 13.2.2.1 Training Program A training program has been established for each VEGP organizational group. At ths time of fuel load, personnel assigned to a particular group will complete the initial training before performing independent tasks or will meet the minimum education and experience required by ANSI /ANS 18.1- ,1971. Y b T W c M&4 m +T2 5 % w k M n d >fu [;& y Aad dw 0+ W f % AAM/ cfm sfl& e aw-~, ,m bY 4 Wjg W =N f i Ii

I i 1! W b m,ucc 'c.c' lg- _ aL d u b a s Yd,a n y a K ~ yw s,~, - y/ a iju k n a c.9 J M L,d,X. 42 /.Wa cA 1 a$ w-3- . nn,..... g. -upcs~ Dw n.4 ,= .4 wnt/ n;clesb doc 8,~ 4 An / a,ja *A~T . uuw QH ~ o / s u X G f:sc M f, e M w & J f e jJ2 A D p f w yda gQ&p eay w J .e a .f % mas 4A Vu Wu. ll)1 o b. i- .i t-e 4-

7.v e 0./A4 W N br .2& St. C' b' AU./~r W.t. Pli, 2k', ' 4 f \\ E x.u E,j. % ir,-n.. y y r a ~ .' &./

As,.

f ['7/k div{ t 1~ s v.- Y~* fA 4.4ph-8, 'WdJ/ lWH fc .C WJ/ GJ4 hP/ kJ., JK .'. No ~ waide huk bashcra w>dA srdd ct ?.- !o. he,,( AB./3);/k l3.22-1 i l Training programs for the following organizational groups have been established. I Health physics / radiochemistry 13.2.2.1.1 Instrumentation and controls 13.2.2.1.2 Mechanical maintenance 13.2.2.1.3 Electrical maintenance 13.2.2.1.4 Shift technical advisor 13.2.2.1.5 No'nlicensed operator 13.2.2.1.6. Licensed operator 13.2.1 Training (instructor qualification) 13.2.2.1.7 General employee training 13.2.2.1.8 Fire team training 13.2.2.1.9 Independent review boards 13.2.2.1.10 Quality control 13.2.2.1.11 Engineering and technical. support 13.2.2.1.12 1 i i The syllabus for each training ,program, including the duration and the organizational group -receiving the training, is described in the following subs'oction or paragraphs: 13.2.2.1.1. Health Physics / Radiochemistry Training Program A. -Initial Training Personnel assigned to perform health physics / chemistry duties will complete this initial training program before being assigned to perform independent health physics /chen.istry tasks. i

m, c,, ~ u. I {} VEGP-FSAR-13 L Approximate Curriculum outline Duration 6 -/o b General employee badge and health Ah ) q physics training Respirator training 2h Industrial safety and first aid 4h New emp.loyee fire training 2h New employee quality assurance 1h ( -) training General pressurized water reactor 1 week systems and procedures General balance of plant systems 1 week and procedures Health physics fundamentals

2. weeks Radiation protection 1 week Chemistry fundamentals 1 week Mitigating core damage (commensurate 4h 4

with responsibilities) 1 B. Continuing Training 'After completing' initial qualification, health [L physics / chemistry personnel will usually attend a' (' program each quarter from the following health n physics / chemistry schools. Approximate Curriculum Outline Duration Advanced health physics 3 weeks Analytical. chemistry 1 week Radiochemistry 1 week Corrosion 16 h t C. Annual Requalification Training.or Exemption Testing Health physics / chemistry technicians will complete annual requalification training or exemption testing 'to make them aware of and review important. changes made to plant emergency and disaster, radiation protection, security, and respirator procedures. D. Initial Foreman Qualifications (and Student-Engineers) Normally, foremen'will have progressed from the initial qualification program through most of the continuing courses before being selected for their position. For personnel who do not follow this path, h a special qualification program will be designed to D' ensure that-all elements of the initial qualification 13.2.2-2' Amend 4 2/84 . u. a .-. w. :.. ~.. - ~... - - - -. - - .... ~ -.

I [ *c . e r..,,,..... h[ F VEGP-FSAR-13 program are completed and. selected elements of the continuing program are addressed as appropriate. This special program may include exemption testing to 3 ensure-qualification. Foremen will receive th'e following training. Approximate (* Curriculum Outline Duration Plant administrative controls for 3 days supervisors Labor relations 3 days New supervisor (or leadership) I week E.~ Continuing Foremen Training ~ Foremen will normally attend continuing training on'a quarterly basis until all programs from the VEGP l7 health physics / chemistry schools are completed. F. Health Physics / Chemistry Supervisor Qualifications and r Training The health physics / chemistry supervisors will have the qualifications required of health physics / chemistry foremen and.will normally attend a similar continuing training program. G.- Incumbents an'd New Employees Personnel with experience that exceeds Nuclear Regulatory Commission (NRC) commitments may fill a position in the career path provided that the health physics / chemistry superintendent certifies that the employee's experience qualificatioris exceed the -( - position requirements. The training department-may E( also. accept prior training or experience to fill specific course requirements. 13.2.2.1.2-Instrumentation and Controls Training Program 'A. Initial Training New employees assigned to perform instrumentation and controls maintenance will complete this-initial training program before being assigned to perform / independent trouble shooting. ,} Amend. 4 2/84 13.2.2-3 Amend. 7 5/84

a..:., a l...

-wu., L-e " ' r...

= f $} -n......- { VEGP-FSAR-13 Approximate Curriculum Outline Duration G mi o h f General employee badge and health 6-h-c ( physics training Respirator training 2h Industrial safety and first aid 4h New employee fire training 2h New employee quality assurance 1h training f( General pressurized water reactor 1 week systems and procedures General balance of plant systems 1 week and procedures Mechanical / electrical skills for 1 week 1 instrumentation and controls Mitigating core damage (commensurate 4h with responsibilities) 4 B. Continuing Training { After completing initial qualification, instrumentation and controls personnel will usually (' attend each quarter a program from the following l[ ) instrumentation and controls schools. Approximate = Chi culum Outline Duration Analog electronics 1 week s. Digital electronics 1 week Test equipment I week Process instrumentation 1 week Precess control systems I week 5: 1 C. Annual Requalification Training or Exemption Testing Instrumentation and controls technicians will complete w 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) 1 4 Normally, foremen will have progressed from the initial qualification program through most of the continuing courses before being selected for their position. For personnel who do not follow this path, ( a special qualification program will be designed to ensure that all elements of the initial qualification 13.2.2-4 Amend. 4 2/84

VEGP-FSAR-13 program are completed and selected elements of the continuing program are addressed as appropriate. This special program may include exemption testing to ensure qualification. Foremen will receive the following training on a priority basis. } ' Approximate y Curriculum Outline Duration j( Flant administrative controls for 3 days supervisors Labor relations 3 days New supervisor (or leadership) 1 week E. Continuing Foremen Training i Foremen will normally attend continuing training on a n quarterly basis until all programs from the Mit:R[\\/ER$ fD -N =le:r "l an*{ instrumentation and controls schools are completed, then they will complete selected programs from the electrical and mechanical schools, focusing upon initial qualifications first. ( ,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 appointmont to the position, en a priority basis, the new supervisor will complete the following training. Approximate Curriculum Outline Duration 1C Ele:trical,, pressure vessel, and 1 week piping codes and standards (including nondestructive testing . review') G. Incumbents and New Employees Personnel with experience that exceeds NRC commitments may,fil,1 a position in the instrumentation and controls career path, provided the maintenance superintendent certifies that the employee's experience qualifications exceed the position s 11 ' requirements. The training department may also accept L' prior training or experience to fill specific course requirements. f 13.2.2-5 Amend. 4 2/84 \\bf

f 43, ( VEGP-FSAR-13 %s 13.2.2.1.3 ' Mechanical Maintenance Training Program 1 A. Initial Training 'r Y New employees assigned to perform mechanical ~ ~ maintenance will complete this initial training program'before being assigned to perform independent mechanical tasks. 4 Approximate k, Curriculum Outline Duration G-/0 4 General employee badge training 96Wh([ Respirator training 2h Industrial safety and first aid 4h New' employee fire training 2h New employee quality assurance 1h training General pressurized water reactor 1 week systems and procedures General balance of plant systems 1 week and procedures ( Maintenance fundamentals 1 week [ . Mechanical fundamentals 1 week A B. , Continuing Training. After completing initial qualifications, mechanical maintenance personnel will normally attend each. quarter a program for the following mechanical schools. Approximate Curriculum Outline Duration Pumps and valves - applied heat 2 week ( transfer and fluid flow Po;wer transmission, pneu-atics, I week. and lubrication Machine shop 1 week Pressurized water. reactor systems 1 week maintenance ( Balance of' plant systems 1 week-maintenance C. Annual Requalification Training or Exemption Testing Mechanics will complete annual requalification - (. training or exemption testing to make~them aware of ((l and review important changes made to plant emergency ~ 13.2.2-6 .~

p. 4-[

.n,...... VEGP-FSAR-13 and-disaster, radiati'bn protection, security, and respirator procedures. D. Initial ~ Foremen Training (and Student Engineers) Normally, foremen will have progressed from the initial training program through most of the continuing courses before being selected for their position. "For personnel who do not follow this path, a special training program will be designed to ensure l that all. elements of the initial qualification program are completed and selected elements of the continuing program are addressed as appropriate. This special -program may include exemption testing to ensure qualification. Foremen will receive the following training on a priority basis. Approximate Curriculum Outline Duration Plant administrative controls for 3 days supervisors Labor relations 3 days New supervisor (or leadership) I week E. Continuing Foremen Training . Foremen will normally attend continuing training on a' quarterly basis until all programs from the mechanical schools are completed, then they will complete programs from the-electrical schools, focusing upon the initial _ electrical ' qualifications first. F. Maintenance Supervisor Qualifications'and Training. The maintenance supervisors will have the qualifications required of maintenance foremen and E will normally attend a similar continuing training program. After initial appointment to the position, on a priority basis,- the new supervisor will complete-the following training. Approximate ( Curriculum Outline Duration Electrical, pressure vessel and 1 week . piping codes and standards (incitading nondestructive testing review) 13.2.2-7 ..,.a.5%.e 4., .o*

VEGP-ESAR-13 G. Incumbents and New Em')ioyees Personnel uith experience that exceeds NRC commitments may fillia position in the mechanicad. career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific c6urse requirements. 13.2.2.1.4 Electrical Maintenance Training Program A. Initial Training New employees assigned to perform electrical maintenance will complete this initial training program before being assigned to perform independent ~ electrical trouble shooting. Approximate Curriculum Outline Duration 6-/o 4 1(.- General employee badge training <L I k \\. Respirator training 2h Industrial safety and first aid 4h New employee' fire training 2'h New employee quality assurance 1h training General pressurized water reactor 1 week systems ~and procedures General balance of plant systems 1 week and procedures Maintenance fundamentals 1 week Direct current fundamentals 1 week Alternating current fundamentals 2 weeks Electrical safety, drawings, and I week l10 test equipment-B. Continuing Training After completing initial qualification, electrical maintenance personnel will.usually attend each quarter a program from the following electrical schools. --( (=; ~ 13.2.2-8 Amend. 10 9/84 p 4 d ' '

.~ 4 { f f . VEGP-ESAR-13 eA s s Approximate curriculum outline Duration ~ Protection devices, control devices, 3 days and motor control centers 1 Alternating current modes and 3 days 1' generators Direct current motors and 1 day 4 generators ( Primary systems maintenance 1 week j .\\. Secondary systems maintenance 1 week . Solid state theory 3 days Batteries, chargers, and inverters 1 day ~ Welding machine maintenance 1 day Pyrotronics fire detectors 1 day Conductors and cable terminations 1 day Motor-operated valve maintenance-1 day Switchgear and breaker maintenance 3 days C. Annual Requalification Training or Exemption Testing Electricians will complete annual requalification training or--exemption testing to make them aware of .1 and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures. knitial Foremen Qualifications (and Student Engineers) D. s.--. Normally, foremen will-have progressed from the initial qualification' program through most of the continuing cou'rses before being. selected for'their position. For personnel who do not follow this path,. a special qualification program-will be designed to ensure that all elements of the initial qualification program are completed and. selected elements:of the ~ .? continuing program are addressed as' appropriate. This ~ special program may include exemption testing to ensure. qualification. Foremen will receive the following training'on a priority basis. ~ . Approximate Curriculum outline Duration Plant administrative controls for 3 days supervisors Labor. relations. 3 days-New supervisor'(or leadership) I week 13.2.2-9 -.2***'::~kT'*:T****":D*N": .--.-.-.--.2.

f VEGP-FSAR-13 E. Continuing Foremen Training Foremen will normally attend continuing training on a quarterly basis until all programs from the electrical schools are completed, then they will complete programs from the mechanical schools, focusing upon the initial mechanical qualifications first. 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, on a priority basis, the new supervisor will complete the following training. Approximate Curriculum Outline Duration Electrical, pressure vessel and I week piping codes and standards (including nondestructive testing review) G. . Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the electrical career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements. 13.2.2.1.5 Shift Technical Advisor Training Program A. Education Requirements Shift technical advisors will have a bachelor's degree in a scientific or engineering discipline. B. Training Program The candidate holds or has held an NRC senior reactor operators-license for that type of reactor, or the candidate completes a Georgia Power Company (GPC) shift t 4Aechnicaladvhortrainingprogramu..z-ti.;( (' s>d a rs.2.2 - B = 13.2.2-10 i

~ VEGP-FSAR-13 1. A e classroom and plant formal training co ering reactor theory, design o a ch stics, transient analysis, ( admin 've controls, an,d leadership. 2. A 4-week o ations training program covering normal, trans t, and accident plant conditions, with a minimum o 80 h of simulator manipulations.

(

3. A comprehensive exami tion process including written, oral, and manip lation examinations. 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. ift technical advisors will receive the following. c1 sroom training. Approximate Cury%culum Outline Duration Introd ion nuclear power plant 1 week system a ' cal physics, electri d electronics Atomic phys nuclear physics 1 week Reactor core sics 1 week Reactor operati s 1 week Heat transfer an fluid flow 1-week Chemistry, health

ysics, 1 week' radiation shieldin and nuclear power plant material

[ Pressurized water react technology 6 weeks l3 ( and system design g Applied theory and thermod amics 1 week and technical specificatio L. l 13.2.2-11 Amend. 3 1/84

/~f/j i \\ VEGP-FSAR-13 ( Approximate Curriculum Outline Duration Transient / accident analysis, 3 week (~ mitigating / core damage, and-emergency procedures Admin rative controls and 1 week ement training P rati for final examination 1 week a f 1 examination { Shift tech ca advisors will receive the following transient an rations training. Approximste Curric um Outline Duration Normal systems o ration, plant 1 week startup, power ntrol, and plant shutdown Emergency systems ope ation, minor 1 week malfunctions, plant

ansients, C

and core physics Trip transients and Final Safety 1 week Analysis Report accident Major Final Safety Analysis eport 1 week' accidents and acciddents be d the design analysis D. Requalification Training for Shift Technical Advisors Shift technical advisors will attend the same requalification program as NRC-licensed operators. Persons noc actively performing t t technical f advisor functions for a period of - ~ - =. or longer / shall, prior to assuming responsibilities of the position, as a minimum receive training to ensure they ( are cognizant of facility / procedure changes that 4 L occurred during their absences. Persons not performing the shift technical advisor function for a period of 6 months or longer shall, prior to assuming the responsibilities of the position, -/ undergo an individual requalification program. ( 13.2.2.1.6 Nonlicensed Operator Training Program A. Initial Training After the start of fuel load, all personnel assigned to perform independent plant equipment manipulations 13.2.2-12 Amend. 4 2/84

f 5; . ~. C.. VEGP-FSAR-13 will either complete this initial training program, be qualified to the shift technical advisor level or certified.to the senior reactor operator level, or C have experience which is equivalent to the following program. Approximate " Curriculum Outline Duration G -/o 4 General employee badge and health physics training Respirator training 2h Industrial safety and first aid 4h New employee fire training 2h New employee quality assurance 1h training General pressurized water reactor 1 week systems and procedures General balance of plant systems 1 week and procedures and one of the following Turbine building systems and 4 weeks procedures

l Auxiliary building systems and 4 weeks procedures B.

Continuing Training After completing initial qualifications, the nonliceased operator will complete qualification on the plant systems which were not taught during the initial training. Normally, the nonlicensed operator will qualify on all systems outside the control room and containment during the individual's first 3 years (. in the plant operations department. .C. Annual Requalification Training or Exemption Testing Nonlicensed operators will complete annual requalification training or exemption testing to make (. them aware of and review important changes made to plant emergency, radiation protection, security, and respirator procedures. D. Nonlicensed operator Progre.ssion After completing a license training program, many operators will progress to licensed positions. The licensed training programs are described in subsection 13.2.1. 13.2.2-13 Amend. 4 2/84 .,,.. =.. ~....-- 4

f 33 4 i VEGP-FSAR-13 N 13.2.2.1.7 Instructor Quilification Program and Certified Instructor Requalification Program This program has been outlined in paragraph 13.2.1.3.34,.- .0m ed A**so 144 0 C ~ yb & p

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,ouaT9.s.J(d. 9 e. 1. -13.2.2.1.8 General Employee Training (Badge Training) A. General Training All personnel who are granted unescorted access to the VEGP's protected area will receive the following training or, if they have completed a similar. program at another plant or facility, will be tested to verify. satisfactory knowledge of VEGP procedures. i . Approximate Curriculum Outline Duration General description of VEGP M'h i facilities, general VEGP f j procedures and instructions, .eedi;1.vi 1 hr lt'. ..J ..Z. my ( pr.ngr.aadL station emergency plans, industrial safety program, fire l. protection program, security i ' program, and quality assurance i, program e f 0)[J.Ae/ Hb i ? Ao Cwi4 e.e k m - uA wl+ M& i I

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d&W4 e4 6 i e4 sun oc.>p dak u l l Jy,A&~ p 8 (JA ( $ M dLs seduDL \\ cs,4 acs rq w21 as6 / w & t3 a^e n A & ed 4~,- ocdd k esw~l$ 8 / gAlpc & & 7 N D W l, 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. C. Temporary Personnel Temporary maintenance and service personnel will be trained in the following: Approximate Curriculum Outline Duration Industrial safety, security 6h procedures, radiation protection program, and emergency plan Prior to completion of the above training requirements, only escorted access will be permitted. i ~

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CudeJun DuMk be"4.s'b? ([) Indoctrination or the plant fire righting plan with specific identification or each individual's responsibilities. 3 ( ) Identification of the type and location of fire hazards and associated types or fires that could occur in the pl. int. (h) The toxic and corrosive characteristics or expected products of combustion. I (e) Identification or the location-6 -or fire fighting equipment fo r ] each fire area and familiariza-tion with the layout or the plant, including access and egress routes or each area. (5) The proper use or available fire fighting equipment and the corrective method or fighting i each type or fire. The types or l, fires covered should include fires in energized electrical equipment, fires in cables and cable trays, hydrogen fires, fires involving riammable and combustible liquids or hazardous process chemicals, fires result-ing from construction or modirl-cation (welding), and record file fires. to (f) The proper use of communication, lighting, ventilation, and-emergency breathing equipment. ?

5l Y Cu n'eu /um GJbe K~., ;. /- r > ba tl A The proper method for righting (g) fires inside buildings and confined spaces. The dircction and coordination (3) of the rire righting activities (rire brigade leaders onlyl, Dotalled review of fire righting (d) strategies and procedures. (g) Review of the latest plant modifications and corresponding chances in fire righting plans. B. fix aoc4 i A d % n%A6s: Q.~&y k.>. N,'// Le p-v,je / Jo e c 5 G h <,'.de menf e,- h <enb-> c/s.sg e - ja % Sl<e p, echo p v-aoc/,o<oude re?re6 -b-a,he'ag. fefwla cfm T cauua;widtu AAJf J>p q<J< A he : d,,,~de fj, 7r,/c3 d. even k yon.s. i red.& 01)~d(r)] Aa'/4 r 4 // Le p' e <Co-- ed D<,'/4 : Q u<< h fy aod & }c.d oae c/<<'// pe< yen ~r // Le pav&e/ un enooud ce d h de Ar#~ ne N o-ree A der: o! Ike-S,~, e L.yde. D,lds sb// be <eto'AJ'i > r A'eI-d ? C,-eyeey A ensee MJ e c h' men ter o f He. b,,j. de p 4,p. 4, ;a a'/ car + hoo c/,,/d Fv M < d /e < d suce pe< y en e. pe,yev. of,ii/ sL // /e. pe A-ec/ oa a %4' 1,'O

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f.20 L s t C. /b./ /LL $h Practice sessions will be held at = least once per year for each shirt brigade on the proper methods of righting possible plant f i re s, breathing appa ra tuses, and r" under strenuous condi tions. c ac, /Y7 * *" b # v d ~ M G "' r f a [,, '_ ]p J// evf*

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,, Ja., Iy haI.or',1 b Y,,A'o(O] .r + A)] p-se f Ht CL N t instruction or the fire brigade will _i be provided by quallried indivittuals aii suitably trained in righting the 5 types or rires that could occur in A 4., the plant, using the types or equip. e 7 f. 17 /. O 2 4,, r4 <J -j ment available in the plant. N f ' -E r--' 5 l-o ,e ) o' ' a' ', ,,.,.,,,1 'g l [ A p. c,n c? f / /* 2 -l e YN N A 3. m r e, g epm e i, r 3 y ] [. [eae,-J' SuployeL ' ' $ O h C l-p;;.c p,.,L J o'a f<<<. wag Ev i* W.4 { i s, w, u,wc) n es co Adne y ( ,LJ,fe ,bs h uch:as & f 6 E ',lef*' A adA h o l ' 3, J.,s J,c,: . I App <>pm. <e n-, ,) g,, f.,,'e, a,,el G e b.<< e - p ~AA.~ J 4' y. 3\\ & m. m b % #6 -3 cc-y) Af,',, god rvrpass'5Ny "P*U Ai"'T

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- = VEGP-ESAR-13 (* App xim e Curriculum Outline Dur ti strategies, type and location C-. of potential fires, forcible entry, fire fighting equipmen, field practice on demonstra on fires, and fire protection system B. Quarterly Training Series Quarterly training willl be/ pi v d to each fire brigade member to revie cl ai t in the fire protection p o ram and ro is refresher training. By the use of gaa erly%e tr i the initial classroom topics will e pea e ry 2 years. Quarterly ^ drills shall be erf r and at least one drill per year will be er rm 1...nounced to determine the readiness of h fi brigade. Drills shall be repeated in fic nt frequency to ensure that each member of the bri ade participates in at least two drills per year ~ C. Annual Pract'ce Each me r of the fire brigade will experience actual fire e inguishment and use of emergency breathing appar us on an annual basis. Further, at least once .per ear a drill shall be performed on a "back shift" f each shift fire brigade. 13.2.2.1.10 Independent Review Boards l A. Initial Training f Members of independent review boards have specialized l expertise and qualifications to independently and collectively review all aspects of plant activities. The function of training for these individuals is to provide them with information concerning the unique aspects of VEGP's design and operation. The following initial training will be provided to all members of the review boards who are not experts in VEGP. operation. -( 13.2.2-15 ...e +.w .....s :l.A. -.. ~ _. -

(o e VEGP-FSAR-13 ~ N Approximate Curriculum Outline Duration Classroom Reactor theory, health physics, 1 day and primary systems Primary systema, emergency systems, 1 day heat removal systems, and radiation waste and monitoring systems f_ Heat transfar and fluid flow, 1 day ( secondary systems, electrical systems, and accident analysis Nuclear instrumentation systems, 1 day nuclear control systems, and integrated plant control Reactor protection systems and 1 day safety injection actuation system Simulator and classroom Plant heatup, reactor and plant 3 days g startup, and plant cooldown j Plant transients 1 day [. L Plant accidents 1 day A B.. Continuing Training Annually, review board members will receive approximately'16 h of training to review significant industry events. When appropriate, the simulator will be used to demonstrate these events. 13.2.2.1.11 Quality Control Training Program A. Initial Training (L' Personnel assigned to perform quality control inspections will complete this initial training program before being assigned to perform independent inspections. Approximate ( Curriculum Outline Duration General employee badge training 6h Respirator training 2h Industrial safety and first aid 4h ( New employee fire training 2h ({. 13.2.2-16

e - o-~. .bi f [\\.(j-- VEGP-FSAR-13 ~ N Approximate Curriculum Outline Duration sf New employee quality assurance 1h ( . General pressurized water reactor 1 week _ training systems and procedures General balance of plant systems 1 week and procedures 1

f Quality control codes, standards, 1 week: (L and procedures Nondestructive testing.and welding 1 week-B.

Continuing Training After completing initial qualification, quality contrci personnel,will usually attend annually a program.to improve their quality control skills or a j program-from the electrical, mechanical, or instrumentation andicontrols schools. C. Annual Requalification Training or Exemption Testing -(- - requalification training or exemption testing to _ Quality control specialists will complete annual review important changes to plant emergency, radiation protection, security, and respirator procedures. J - D. .IncumbentsLand New Employees Personnel with experience.that. exceeds NRC commitments may. fill'a position in the' quality' control career path - provided the plant manager certifies that the employee's experience qualifications exceed the: h position requirements. The' training department may also: accept prior--training or experience to fill specific. course requirements. l, '(f g; .13.2.2.1.12 Engineering and Technical Support h' A.- Initial Orientation Training $ L( g'.. power plant experience will complete the following Professional personnel who do not-have prior nuclear. orientation program normally during the first 6 months ~ at VEGP;- 13.2.2-17 .~......a w ..r... e.>... ~ m -~.,, - - ...,...-__.---.,-.~_._--....-.,.--.,....,..-,......---.e.,...-. 4 _ ~ - ~ ..r,- m

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VEGP-FSAR-13 Approximate Curriculunt_ Outline Duration General employee badge and health 6h physics training Respirator training 2h Industrial safety and first aid 4h New employee fire training 2h New employee quality assurance 1h training Reactor theory, health physics 1 day and primary systems Primary, systems, emergency systems, 1 day heat removal systems, and radiation waste and monitoring systems 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 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. 13.2.2.2 Shift Technical Advisor Training Program The shift technical advisor training program is described in paragraph 13.2.2.1.5. 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. ~ >% hsw /e u S n, / J w f s o&pa L 5 ~ h jl u >4 W *agA M e+f % ;. 4 a ; G k . w sy-M &4m

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VEGP-FSAR-13 { -13.2.2.4-Initial Position Task 2nalysis The training programs described in section 13.2 are the result Ep' -of the initial position task 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 task analysis. Georgia Power Company stresses the use of this 'f. feedback to meet:our overall training objective to train for ( job proficiency. 13.2.2.5 Training Program Syllabus The'VEGP training organization is described in subsection 13.2.1 and figure 13.2.1-1. Georgia Power Company will use the same training programs to qualify its personnel both before and after the initial fuel loading. Almost all programs in this section are considered formal or " classroom" programs. A ~ formal prograra consists of. instruction in the classroom, i laboratory, cimulator, and field which is supervised by an' instructor. Specifically, the shift technical advisor program ..f - '(paragraph 13.2.2.1.5) and the training (instructor qualification) program (paragraph-13.2.2.1.7) use some on-the- , job training before the individuals in these organizational [ groups'are permitted to perform job tasks. h L '13.2.2.6 Reactor Operations Experience Training ~ Reactor operations experience training will be provided ns

outlined in paragraph 13.2.2.1 by using the VEGP simulator, preoperational test program, and observation of other light--

water reactors. ( 13.2.2.7 Differences in Training Programs L LThe 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 pregram used for l: fire brigade members-is described in paragraph 13.2.2.l.9. t L( I L 13.2.2-19 e ... a e.s a.>....:. ...... ~ - - = - -, ~. - - -

y 3, VEGP-FSAR-13

13.2.2.9 Qaini-2rogram-Effectiveness Training program effectiveness is evaluated by either written, oral, or practiced demonstration examinations for each employee..

g. Figure 13.2.2-1 is a schedule showing the start of each portion of the nonlicensed plant staff training program in relation to the schedule-for preoperation tests, fuel load, and expected time for license examination. Since all of the training programs in this section are used for both units before and after fuel load, after a particular program is started, that program will be available for use any time there is a need to qualify additional personnel. At the time of fuel load, sufficient VEGP personnel will be qualified in each organizational group to meet the staffing requirements of . 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. r ( C.

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m.- -... VEGP-FSAR-13 TABLE 13.2.2-1isHEET1OF ) MITIGATING CORE DAMAGE TOPICS INTEGRATED IYIO O R PROG Classroom Topics Analytical objective C Unacceptable safety results for abnormal o erational transients Un' acceptable. safety result for acciden s Approach to safety analysi q General Abnormal operational t ari ts Accidents Barrier damage evalu a Analyses of abnormal opera iona transiests events resulting in a nuclear system ressure i crease Events resultin n a water temperat2r L ecrease Events resultin i posi ive react Lv insertion Events resulti i reatorvyssel gt ant inventory decrease l Events resu n a e re coola ty L w decrease Even resu in a ore coo t low increase g Even s esul in e cess of co ant inventory Loss of ab lit of the contr 1 room Analysi .of d kgn sin accq nts Intrei ' ti p i Control d dro acci ent Loss-o olan accid t Refueling acc ent Main steam 1 ne break a dent Three Mile I land Unit incident Core cooli g mechanic Potenti ly damaging operating conditions Recog zing core da= age / critical plant parameters Hyd gen hazards during severe accidents N tron monitoring / core recriticality >.,. L.'. e saw e. .rwere ..e. '_- ^-'

~~ ~ ~fQ VEGP-FSAR-13 N TABLE 13.2.2-1 (SHEET 2 OF 2) Simulator and Classroom Topics Natural circulation and core Power op rati s 2cading to > cooling react r tr s and Abnormal operatirig instructions reco ery (, Introduction to emergency operating instructions Health physics review Po r p ations with Radiation monitoring al< tions leading to Radwaste disposal ont lled shutdown Condition II and III events ea r trip and recovery Emergency operating instructiong w malfunctions ~ . Condition II and III events k or steam plant failures; Abnormal operating instructions reactor coolant pump Emergency' operating inst c ons failures; partial and l comple te loss of flow Condition II III en Majpr p] kn equipment Alternative col gtc qu f.il

natural Core recrit4calit ca ation cooldown Condition IV events Pow operations with Loss-of-coolan acci ont ndition iV Iaults Reactor coolant syst m ak Condition IV eve Pow r 'pe at o s o

Steam generator e leak / T onditi IV faults rupture Condition IV eve s and o r Mrations with ( mitigation L c ion IV faults; Extreme emerge cy ope tin ma n steam line break instructio Condition events and Power operations with mitigat n condition IV faults; ( L Inadvert t safety injection anticipated transient without trip ~Cond ion IV events and Power operations with m' igation condition IV faults; Lo a of auxiliary feedwater Three Mile Island accident 0140V l Amend. 7 5/84 ....<u.;.n -.- ,w..'= -a

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pl -[ p p f 1 MONTHS TO FUEL LOAD ' 54 51 48 45 42 39 36 33 30 27 24 21 18 15 12 9 6 3 [ i Pre.- L Fuel Load / perational, Exams and o Tests p Criticality Types and Number of Personnel f-o[ o o <f f Health Physics / Radiochemistry (20) f [/ 2 instrument and Control (20) Mechanical Maintenance (20) Electrical Maintenance (20) = Shift Technical Advisor and Reactor Engineer (6), jj/ Nonlicensed Operator (15)- . Training, instructor Qualification (15) General Employee (170) independent Review Boards (6) [ . Quality Control (6) / If Engineering and Technical Su rt (20) i e :r l TRAINING FOR NONLICENSED voGTLE. l g .Georg. lbwer ELECTR8C GENERATING PLANT VEGP STAFF a unir i u..r. a. FIGURE 13.2.2-1 4J3 9 k

VEGP-FSAR-13 ~ 13.3 EMERGENCY PLANNING s A' comprehensive emergency plan for VEGP Units 1 and 2 is provided as a. separate volume to this application. 4 O 13.3-1

=-

4 VEGP-ESAR-13' 13.4. OPERATIONAL REVIEW Operating' activities that affect nuclear safety are reviewed. The. review program is implemented. prior to initial fuel loading - and ensures review and evaluation of tests'and' experiments,, unplanned events, and proposed change. The program complies within'the. requirements of.10 CFR 50.54 relating to proposed changes, tests,.and experiments. This program is conducted following the' recommendations of Regulatory Guide 1.33, 1977, Quality Assurance Program' Requirements (Operations), and ANSI N18.7-1976, Administrative Controls and quality Assurance for 'the Operational' Phase of Nuclear Power Plants. The pAOND I S=aar has responsibility for safe operation of the ( plant. He is kept abreast of plant operating conditions by the - supervisors who are-knowledgeable and experienced in their. [ areas of job responsibility. The supervisors monitor operating,

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-and maintenance activities as:part of their normaliduties. In. addition, a formal review. program is carried out for changes -to systems, procedures, tests, experiments, and after-the-fact review and evaluation of unplanned events that affect ~ nuclear . safety..This program is" implemented.through standing ~ committees,.as described below. - 13.4.1 ONSITE REVIEW The plant review board serves as a review and advisory group to th pkent managem. The_ plant review board reviews. plant dministration, maintenance, and operations as related to hgdif0 nuclear safety and environmental aspects; ensures these activities are. consistent with company policy-approved-procedures'and operating license l provisions; and makes l recommendations on matt rs brought-before it. = e The p ant view board is comp sed of an interdis plinar I/[' group of: p ant person el. ~ Col actively they pos as the t e. and agre Lof expert e.requi d to re iew unpl ned event 1 sed-hanges to

ystems, rocedur s, tests, and exper ents I pro tha aff t nuclear safety.

he pla t review oard meets at' ritten mipdtes of Ele t-on e'per-cal dar' mon It. aintains ea me ting. -The details' f the ctivities and' duties ofJthe plant r view board are des ribed in plant procedures. t' ? 4 13.4.1-1 h..----E wm+.+ -m.w-4 J ve .e- ,.,a-- y ty n m pyryywwyw -y-y ww -ew-*- w-g- 9--'-ay'- 7g--A T--< +y Mye P =e--

13.4.1 Insert b.& Plant staff The Plant Review Board is composed of as a minimum one 4 from those disciplinary groups ace listed below: g Operations Maintenance Quality Control Health Physics or Chemistry Regulatory Compliance Plant Engineering and Services Collectively these mumbers possess the type and degree of expertise required to review unplanned events, proposed changes to systems, procedures, tests, and experiment that affect nuclear safety. The chairman and vice chairman of the PRB are designated by the GMVN0. The minimum quorum of the PRB will con-sist of the PRB chairman or vice and four members. The PRB meets at least once per calender month. The Plant Review Board is specifically responsible for the following: a) Review of (1) procedures which establish plant wide administrative controls to implement the Q.A. program or technical specification sur-veillance program, (2) procedures for changing plant operating modes, (3) emergency and abnormal operating procedures, (4) procedures for effluent releases, (5) fuel handling procedures. b) Review of (1) program required by technical specifications, (2) pro-posed procedures and changes to procedures, equipment or systems which involve an unreviewed safety question as per 10 CFR 50.59. c) Review of proposed tests and experiments which involve an unreviewed safety question.- d) Review of proposed changes to the technical specification. e) Review of the report of the investigation of violations of the techni-cal specification which covers evaluation and recommendations to pre-vent recurrence. f) Review of all reportable event, g) Review evaluations of plant operations to detect potential nuclear safety hazards. h) Performance of special reviews, investigations or analyses and reports thereon as requested by the GMVNO or the Safety Review Board.

1) Review of the security plan and implementing procedures and submittal of recommended changes to the GMVNO.

j) Review of the emergency plan and implementing procedures and submittal of reconsnended changes to the GMVNO. b

k) Review of any accidental, unplanned, or uncontrolled radioactive re-lease in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci for noble gases or 0.02 Ci of radiofodines for gaseous effluents. The PRB's authority is as indicated below: a) Recommend in writing to the GMVNO approval or disapproval of items (a) through (d) above, b) Render determinations in writing with regard to whether or not each item (a) through (e) above constitues an unreviewed safety question ~. c) Provide written notification within 24 hours to the vice president and general manager of nuclear operations and the Safety Review Board of the disagreement between the PRB and the GMVNO ; however, the GMVNO 4 shall have responsibility for resolution of such disagreements to $ The Plant Review Board will maintain written minutes of each meeting that, at a minimum, document the results of the PRB activities. Further details of the activities and duties of the PRB are described in plant procedures.

n - 1 VEGP-FSAR-13 13.4.2 INDEPENDENT REVIEW The SAFETY REVIEW BOARD (SRB) 'provides an independent review and audit of designateo activities in the areas of: I a nuclear power plant operations; b nuclear engineering; c chemistry and radiochemistry; d) metallurgy; e) instrumentation and control; f radiological safety; mechanical and electrical en quality assurance practices.gineering; and g h Specifically, the SRB will review: a) the safety evaluations for changes to procedures, equipment, or systems; and tests or experiments completed under the provistens of 10CFR50.59 to verify that such actions did not constitute an unreviewed safety question; b) proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10CFR50.59; c) proposed tests or experiments which involve an unreviewed safety question as defined in 10CFR50.59; d) proposed changes to Technical Specifications or Operating License-e) violations of codes, regulations, orders. Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f)significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety; glallthe results of the PRB's review of all reportable events; h recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and

1) reports and n'estings minutes of the PRB.

In addition, periodic audits of plant activities will be perfortred under the cognizance of the SRB to evaluate: a) the conformance of plant operations to provisions contained within the Technical Specifications and applicable license conditions; b)theperformance, training,andqualificationoftheplantstaff; c) the results of actions taken to correct deficiencies occurring in plant equipment, structures, systems, or method of operation that affect nuclear safety d) the performance of ; activities required by the Quality Assurance program; e) the Emergency Plan and implementing procedures; f) the Security Plan and implementing procedures; g) the Fire Protection Program and implementing procedures; and n) any other area of plant operation considered appropriate by the SRB or the Executive Vice president of Power Supply.

13.4.2(continued) The SRB will report to and advise the Executive Vice President of Power Supply on matters related to their responsibilities. The SR8 will be composed of a minimum of seven persons who as a group provide the expertise to review and audit the operation of a nuclear power plant. The Chairman-and Vice-Chairman and other members shall be appointed by the Executive Vice President of Power Supply or other such persen as he may designate. No more than a minority of the SRB will be members of the on-site operating organization. All alternates will be appointed in writing by the absent member to serve on a temporary basis. However, no more than two alternates will participate in SR8 activities at any one time. Consultants may be used at the discretion of the Chairman of Vice-Chairman to provide expert advice to the SRB. SR5 training is discussed in section 13.2. The minimum quorum of the SRB necessary for the performance of SRB review and audit functions consists of the SRB Chairman or Vice-Chairman and l at least three SRB members. No more than a minority of the quorum will have -line responsibility for operation of the plant. ' eports of SRB activities will be prepared, approved, and distributed as R described below: 4 a) minutes of SR8 activities will be prepared and submitted to management within 14 days following a meeting; b) reports of certain reviews will normally be submitted to management within 14 days following completion and SRB approval of the review; c) audit reports will normally be submitted to n!anagement within 30 days following completion anc SR5 approval. ii. I l l l I [. W -,:-

f; -Orm few l3j NN -lemMM Nk pgNW Et4L kspg VEGP-FSAR-13 '13.4.3 INDEPENDENT SAFETY ENGINEERING REVIEWS The independent safety engineering group will perform ~ independent reviews of plant operations in accordance with item 1.B.l.2 of NUREG-0660 as clarified by NUREG-0737. The function .of this group is independent of the safety review board or the plant _ review board. The independent safety engineering group will be comprised of a minimum of five technically competent individuals who will report.to an appropriate independent. level of management. The independent safety engineering group will review appropriate sources of plant design and operating experience information in view of improving plant safety. They will also review various plant activities to provide independent . verification of correct performance of these activities. The independent safety engineering group will provide a monthly report of-their activities to advise management on the overall-quality and safety of operations. i ( - e f .\\., 13.4.3-1

VEGP-ESAR-13 13.5 PLANT PRCCEDURES This section describes administrative, maintenance, and operating procedures that will be used by the operating organization to ensure that routine, off-normal, and emergency activities are conducted in a safe manner. Operations affecting safety will be conducted in accordance with detailed written and approved procedures. 13.5.1 ADMINISTRATIVE PRCCEDURES .fase k 13.5. I 13 .1.1 ?rer *=*4^^ ^' **^^aaures y. respons(ble for initi.ing, "+'r.t[--puidtend--**We Thed- ~ prepar'in ' 'ects under/their respo[g pi' ant; procpui[; w.ch/ rev ing, ar[approvin sibility. /They a afsp a< ldress/su r ensurf'ng that qheir section's work s pe rfdrmed \\ r esponsible i n accordance th the latest a'pproved proqed_ur .V /fJroc dul r k 0 $ / )

3.5.1.2 1es,, inst ctJcCpoJicTes,

pro g p[rovi ~ T)(es tices, or guid line for the p ntAstaff. /they w be y r f omplete4'at leasy 6 mont sjprio to }(nit 1 initial f 1 c l oading. A lministrative procedures w' ensure that access to t e c antrol room is limited a th the lipes of au, thor.it.y,, r esponsibility,.and suc ssiod i the/ control room ar< r jith(ssarea' men'ts eatabli'shed. This is/ accokdan equilre of NUREG-0737, item I.C The lim _it acce is's-1'own in figure 13.5.1k V Acp rat Aip ocedu wi c,1ud e,a s f inyfxpe c, from thin out et a er e ators an 9the lapprgpriate ersonnp n accordag e with_. .NLRfG-07G7, em 1 .5. These pr edures will 4 ~-it re-"4 "4 emss to imit c,vertime.as de scrib def:rn section 6 of the' Technical Specifi ations,Iin / accor nce with NUREG-0737, item I.A.1.3, and' as rev. sed.in l y y Oc. :rien y==*4e intter 82-1 N cl rl j anhos' pg= gdy={opsd br%t%or(emp6 ry 13.5.1-1

VEGP-FSAR-13 Conformance with Reaula*ery nuide 1.33 is discussed in sect'on L v. The following are descriptions of the adminisica 2ve p. cedures that will be prepared for VEGP Units 1 and 2. f A. Op -ations Administrative Procedures The pu. ose of these procedures is to provi instruct ons to ensure that plant operatio are conducted 'n an effective, consisten; man r in accordance ith the operating license, p nt procedures, nd applicable regulatory .uirementa as follows: 1. Procedures w 1 comply with the revisions of 10 CFR 50.54(1 through (m). A procedure whic outlines s ift supervisors duties will be in onforman e with item I.C.3 of NUREG-0737. 3. Shift relief and turn ve procedures are deve oped to ensure that require signed checklists and logs have sufficient i ormation to ensure plant status is known by op a ors, in accordance w Lth NUREG-0737, item I.C. 4. Special orders proc dures p ovide for both temporary instruc* ons to ad 'ress subjects not covered by exist g procedure and for special instructions fo the evening a d/or night sh.ft. 5 The authority nd responsibilit; s of the sh Lft technical adv sor are described n subsectio n 13.1.2. B. Eq2ipment Con ol Procedures Pr ocedures or the control of equipment are written to pr avide co trol of purchased and nonconf rming ma :erial d the status of plant equipme t. Procedure for removing safety-related e ipment from service nd returning it to service will sure that the oper bility status of that equipment is known, in cor form nce with item II.K.l.lO af NUREG-0737. 4 The e procedures crude psv<. vu vu une foi owi 1. Work authorizations. 13.5.1-2

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4.'e. eviddt'. h() r&1&lf4bl h6 5b4b6 6 4'I f W 'l h sc,v,y,, ft'v'd $ $0- etMi & & Lf$wceMtY 3nd NG () hts'ut; kl0 Nt' O 0-gri .ww. ut tc <e,, m g s js S k a l l *lt L VclfC$(~lGvt wll{ f@ nrbt Qd 4y ait. H en:t [N(*% h sti ne'e.' t H ct k& ~t s >%t N c' at fc'.MthC 'c' bb' IC 'd % e nce, n wse y,wate Ns aa,ws he mo'eneds. IhdrH [* C,, aatt i 4 L K. lal.1 Sl;'$li $ ~ 6'^l 3 'l, h AME /VIS. 4 - M;76, Se: h c-1 Gr ed be eiMax wn -T, 2,. h +Elkk a +c e p df me d ce d M I- "J (. Maintenance and Modification Administrative Control Procedures Maintenance of equipment and plant modifications important to plant safety are performed in accordance with written procedures as described in paragraph 13.5.2.2. Administrative controls are provided to ensure compliance with applicable codes, regulations, and requirements. K 'x. Pire Protection Procedures The VEGP fire protection program is governed and implemented through the use of fire protection procedures. These procedures provide guidelines for the following: administrative controls, system operation, fire fighting activities, fire brigade and general personnel training, and agreements with local offsite fire departments, as described in subsection 9.5.1. l Crane Operation Procedures Crane administrative operating procedures require that crane operators who operate cranes over fuel pools will be qualified and conduct themselves in accordance with ANSI B30.2-1976 (chapters 2 and 3 ), Overhead and Gantry Cranes. M [. Temporary Procedures l Temporary procedures are issued as required to provide detailed instructions for specific jobs that are of a i j specific duration. l M K. Emergency Core Cooling System Outage Data Collection Procedures These procedures are developed for collection of emergency core cooling system outage data in 13.5.1-3 ~
~ VEG?-FSAR-13 accordance with NUREG-0737, item I.K.3.17: this data will be reper:ed to the Nuclear Regulatory Comm;ssion in accordance with the Te hni:al Spe: fications. O' ](. Initial-Test Program Administration Procedures The administrative procedures that establish centrols 'for that par: of the initial tes: program pr or to fuel load are described in the VEGP startup manual. The administrative controls for that part of the initial test program after fuel load are included in the plant procedures manual. f (. -?lan: Security Procedures i Plant security procedures provide for the implementation of the security plan. (See section ...Q. 4 y 13.5.1-4
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FIGURE 13.5.1-1
4 VEGP-FSAR-13 13.5.2 OPERATING AND MAINTENANCE PROCEDURES 13.5.2.1 Operating Procedures These procedures are for operation of plant equipment and will be completed ~approximately 6 months prior to initial fuel loading. These procedures are developed and provided to. ensure an effective system for *.*erifying the correct performance of ^ operating activities and reducing human error. This will meet the intent of NUREG-0737, item I.C.6. Conformance of these procedures with Regulatory Guide 1.33 is discussed in section 1.9. Although format can be varied depending on their nature, these procedures will usually have the following format: 1.0 PURPOSE The purpose for which the procedure is intended will be briefly and clearly stated. 2.0 PRECAUTIONS AND LIMITATIONS Precautions will be established to alert the individual performing the' task to those important measures which will be used to protect equipment and personnel or to avoid an abnormal or emergency situation. ' Limitations on the parameters being controlled and appropriate corrective measures to return the parameter to -the normal will be established. Control band may be specified where applicable. 3.0 PREREQUISITES OR INITIAL CONDITIONS Each procedure will identify those independent actions or procedures which must be completed or those plant conditions which must exist prior to its use. -Prerequisites applicable only to certain sections of a procedure will be so identified. 4.0 MAIN BODY The main body of a procedure will contain step by step instructions in the degree of detail necessary for performing a function or task. Subsections of this section will vary according to procedure type. Format for each procedure type will be concistent. l 13.5.2-1 L:
F: VEGP-ESAR-13 restore normal operating conditions following a transient. _Such actions are invoked following an operator observation or any annunciator alarm indicating a condition which, if not corrected, couli degenerate into a condition requiring action under an emergency operating procedure. F. Emergency Operating Procedures The emergency operating procedures specify operator actions to reduce the consequences of an accident or potentially hazardous condition which has occurred. Operators are required to memorize the immediate operator actions of these procedures. The emergency. operating procedures are developed according to the action plan which incorporates developmental information provided in the implementation plan guideline published by the 4 Institute of Nuclear Power Operations. . Technical guidelines (emergency response guidelines) and accompanying background / support _information are supplied by the Westinghouse Owners Group. The C generic background / support information is made plant specific. In addition, each generic technical / guideline is-reviewed to determine the information U needed to generate plant-specific procedures. An-emergency operating procedures writer's guide is developed prior to generating these procedures from the Westinghouse Owners Group technical guidelines. In summary, the emergency operating procedures are developed using the Westinghouse' Owners Group technical guidelines, plant-specific background / support information, and the emergency' operating procedures. writer's guide. Each completed procedure is subjected to a two-part review in accordance with the emergency operating procedures verification program. The,first part of this review verifies written correctness,.while the second part ensures technical accuracy. Upon completion of the. verification program, the procedures are tested in accordance with the emergency operating procedures validation program. The validation program -requires that all procedures be validated by at least one of the following (in order of preference'for validation): using the plant-specific simulator; actual testing on plant systems; or detailed review. 13.5.2-3
f VEGP-ESAR-13 13.5.2.3 Other Procedures other procedures are provided in the following areas: A. Health Physics Procedures Plant radiation protection procedures are designed to limit and control radiation exposure and the spread of contamination as well as to meet the requirements of 10 CFR 20 and tne as low as reasonably achievable philosophy. The procedures describe rules and practices or guidelines for personnel protection, radiation surveys, decontamination, handling of radioactive or contaminated materials, and implementation of the as low as reasonably achievable program. The health physics department has responsibility for implementing these procedures and ensuring the compliance of the plant staff with them. B. Laboratory Procedures These procedures describe rules, practices, or I guidelines for tests, analyses, additions, or dilutions with respect to plant chemistry and radiochemistry. The health physics and chemistry n i laboratories are responsible for performing these ( g activities. \\ C. Refueling Procedures t These procedures provide for preparation and performance of refueling operations. They include procedures to disassemble components, refueling equipment preuse maintenance and checkouts, and methods and limits for performing refueling operations. D. Emergency Plan Implementation Procedures These procedures provide rules and practices and designate responsiblity and authority for classifying emergencies and responses to such emergencies. The plant staff has the responsibility to follow these procedures. Procedures in this section implement the emergency plan. 13.5.2-5 L __}}

ML20106C260

Text

Dear Mr. Denton:

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