ML20117E166

Forwards Draft Rev 1 to Fsar,Chapter 13, Conduct of Operations, for Review.Rev Incorporates NRC Comments Per 850219 Telcon & Will Be Published in Fsar,Amend 16 Scheduled for 850410

ML20117E166
Person / Time
Site:	Vogtle
Issue date:	03/20/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-547, NUDOCS 8505100343
Download: ML20117E166 (217)

Text

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Georgia Power Company Project Management Route 2, Box 299A Waynesboro, Georgia 30830 Telephone 404 724-8114 404 554-9961 Vogtle Project March 20, 1985 Director of Nuclear Reactor Regulation File: X3BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-547 Licensing Branch 14 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 VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 DRAFT REVIEW COPY OF PSAR CHAPTER 13, REV. 1

Dear Mr. Denton:

Enclosed for your staff's review are two copies of the subject document.

This revision incorporates the comments made by your staff in a teleconference with GPC on February 19, 1985 and will be published in FSAR Amendment 16 scheduled for April 10, 1985.

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

Sincerely, .

g I

,h, gr. ED I- M' J. A. Bailey g gg, g Project Licensing Manager copio TO.

I I JAB /sm Enclosure PS A xc: D. O. Foster gpg 8 R. A. Thomas gp i G. F. Trowbridge, Esquire i g J. E. Joiner, Esquire NO C. A. Stangler m . rEsM 8 i L. Fowler M. A. Miller L. T. Gucwa G. Bockhold, Jr.

l 0086m 8505100343 850320 l PDR ADOCK 05000424 '

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VEGP-ESAR-13 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION This section 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.

GPC nuclear operations' corporate and plant organizations are responsible for directing activities at VEGP. The organizations described in chapter 13 support and report to nuclear operations for assigned activities.

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.

13.1.1.1.1.2 . Design of Plant and Auxiliary Systems. An evaluation of engineering progress of approximately 85.0 percent and overall completion of approximately 76 percent for Unit 1 and approximately 45 percent for Unit 2 was indicated as of March 1985.

13.1.1.1.1.3 Site Layout with Respect to Environmental Effects and Securit Provisions. Site layout with respect to gpvironmental effects is described in chapter 2. Site security with respect to plant geographical' layout and equipment is described in the security plan.

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VEGP-FSAR-13

13.1.1.1.1.4 Development of Safety Analysis Reports. Overall i responsibility for preparation of the Final Safety Analysis Report (FSAR) rests with Southern Company Services (SCS) t nuclear safety and fuel department. Preparation of the individual sections was assigned to the cognizant technical groups within Bechtel, Westinghouse, SCS, and Georgia Power

Company (GPC).

13.1.1.1.1.5 Review and Approval of Material and Component ,

j Specifications. 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 November 1984 approximately 97.7 percent of the Unit 1 major

engineered equipment and systems have been purchased, with the

} majority onsite or in storage. Approximately 91 percent of the 1 nuclear valves and 97 percent of nonnuclear valves for both units have been delivered.

4 13.1.1.1.1.7 Management and Review of Construction Activities.

1 The Vogtle Project is organized on the project management basis, whereby all groups involved report directly or indirectly to the vice president and general manager-Vogtle Project, who reports

! to the the senior vice president-nuclear power, who in turn reports to executive vice president-power supply. Monitoring 4

and review-of activities by construction at the site are as follows:

1 A. The field operations group under the direction of the project construction manager provides the day-to-day 1

management and planning of the actual physical construction activity onsite, i

.B. The quality control group under the direction of the .

4 manager-quality control provides quality control surveillance and inspection of the construction 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.

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l VEGP-FSAR-13 l D. Support operations personnel control material and equipment availability and ensure that documentation is complete, current, and retrievable.

13.1.1'.1.2 Prooperational Activities I

_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 using a reduced l

size control board and GPC operator input into the control. board control configurations. The design incorporated the human factor design criteria at that time. An independent evaluation on human factor design has been performed en a mockup of the control room. A detailed discussion of control room design review and human engineering factors is described in chapter 18.

Design recommendations based on the mockup review were incorporated in the control board design or defer red for further evaluation. A detail design review was conducted on the as-built control room and utilized the plant simulator.

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 1977. Training programs have been developed for this facility and are described in section 13.2.

, 13.1.1.1.2.3 Development of Plans for Initial Testing. The l- general manager-Vogtle nuclear operations (GMVNO) is responsible for all aspects of the initial test program of the VEGP. As part of his responsibilities, the GMVNO (or his designee) will .

direct the development of the startup manual.

The startup manual defines the startup organization, define the responsibilities of involved organizations and personnel,

! delineates the' qualifications necessary for startup personnel,

! and contains the administrative controls necessary for the implementation of the' initial test program. Also, refer to l . paragraph 13.1.2.2.5 for a discussion of the initial test program.

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! 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 included in the plant procedure manual or startup manual.

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I l VEGP-FSAR-13 13.1.1.1.2.4 Development of Plant Maintenance Programs. The work force assigned to the VEGP will provide qualified maintenance personnel prior to initial fuel loading.

Structures, systems, and components that prevent or mitigate the consequences of postulated accidents that could cause undue l risk to the health and safety of the public will be maintained in accordance with the quality assurance program.

! The maintenance staff will be sized to perform the routine and preventive maintenance workload. The staff will be l supplemented by outside contractors as deemed appropriate by l plant management. Maintenance is performed under the direction of cognizant supervisors and in accordance with accepted work practices.

l The scope and frequency of the preventive maintenance will be i

based on past experience with similar equipment and the manufacturer's recommendations. 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, vendor 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 The GPC nuclear operations organization has overall responsibility for assuring the availability of, providing, or securing adequate technical support for the VEGP. Technical support for the operation of GPC's nuclear power plants has been established and is functioning for its Hatch Nuclear Plant. .

Similar support capability is being planned and will be provided i'

for the VEGP. This capability will be available through the joint efforts of the GPC nuclear operations general office staff

and GPC's architect-engineer / service company, Southern Company Services (SCS). SCS's support will be provided through both an onsite nuclear plant support group and a dedicated Vogtle nuclear operational / support organization in SCS's home office. The SCS site support group will be an adjunct to the SCS home office headquarters' organization. Portions of SCS's obligations may be fulfilled through the use of outside contractors as discussed helow.

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VEGP-FSAR-13

! In fulfillment of the responsibility of GPC nuclear operations,

! the GPC nuclear operations organization interfaces directly with, I

obtains services from, and holds SCS accountable for various support activities including the following:

A. Architect-engineering services required for the l design-engineering of plant modifications, including j maintenance-related design changes, plant

! improvement-related design changes, and design changes or major plant additions as a result of new regulatory requirements and commitments. These services include both conceptual and detail design, issue and maintenance of design drawings and specifications, review / approval l

-of design change requests, incorporation of as-built l notices, procurement, related Quality Assurance functions, etc.

B. Design-related safety evaluation and analysis.

C. Nondesign-related safety evaluation and analysis, i.e.,

operational requirements, technical specification changes, etc.,

D. Inservice inspection and testing (both planning and actual implementation).

E. Nuclear fuel procurement.

F. Nuclear fuel core analysis.

G. Generic safety evaluations on prospective licensing issues.

SCS currently has an organization in place for its " project phase" (Standard Review Plan terminology) scope of responsibility in support of the design, construction and licensing of the VEGP. This organization has both home office and on-site .

responsibilities and capabilities which will be converted into a long-term operational support orga: ization to provide the type support noted above. This organizntion will be inclusive of all major design disciplines and will, as necessary, have the capability to contract for outside specialty technical support where additionali expertise is needed and for major surges in manpower needs.

I 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 vice president-engineering and construction services, the senior vice 13.1.1-5 Amend. 16 4/85

VEGP-FSAR-13 president-nuclear power, the senior vice president-fossil and hydro, the general manager-fuel services, and the vice president and general manager-quality assurance. The quality assurance organization is described in chapter 17.

The principal organizations in the power supply engineering and construction services department providing support to VEGP are mechanical engineering, civil engineering, generating plant electrical engineering, engineering services, and environmental affairs.

l The plant staff may obtain assistance from engineering, i construction, procurement, SCS, and other outside engineering i

organizations as required. Environmental affairs manages and l coordinates the overall environmental programs to obtain permits I and licenses from state and federal agencies. The construction services department may supply technical support when requested to manage field operations for civil, mechanical, and electrical construction work.

i l In addition, the power supply department includes the nuclear l power organization. The nuclear power organization includes the l nuclear operations department, which will be responsible for the l operation of VEGP. This department includes the nuclear generation engineering staff, which provides support in the areas l of regulatory responses, generic issues, long-term planning, health physics, emergency response capability, nuclear training, refueling operations, and general engineering. The nuclear power organization is additionally responsible for management of nuclear operations.

Technical support to plant operations outside Georgia Power Company will be provided by and through'the Nuclear Plant Support l

Department. The SCS Nuclear Safety and Fuel Department provides

! nuclear fuel contract administrative services and provides reload licensing and operating licensing support. Additional outside consultants will be used to provide technical support on an .

l as-needed basis.

l 13.1.1.2.2 Engineering and Construction Services Department.

The engineering and construction services department is part of the GPC power supply organization. The department is headed by j the vice president-engineering and construction services and consists of various groups, i.e., engineering services, l engineering, and environmental affairs. The power supply l engineering and construction services organization chart is shown in figure 13.1.1-2.

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l VEGP-ESAR-13 The primary function of the engineering and construction f

services department in support and at the direction of the nuclear operations organization and other GPC operations includes:

A. Support overall project management and engineering services as requested involving design, budget, procurement, licensing, construction, and startup of retrofit projects for GPC's existing generating plants.

B. Direct and indirect technical and/or licensing interface with various environmental and other governmental and regulatory agencies and concerned public groups.

The educational background, years of nuclear power plant associated work experience, and total years of engineering or science experience of the 145 graduate engineers and scientists in the power supply engineering and services department as of January 22, 1985, are as follows:

e The number of graduate degrees: baccalaureate - 141; masters - 20; doctorate - 1.

In addition, the organization of the vice president-engineering and construction services provides preoperational and/or startup support in the following areas:

A. Development of approximately 53 preoperational test procedures.

B. Computer software support in the area of VEGP 1 and 2 emergency response facilities (ERF) computer.

C. Qualifications of Class 1E motor insulation.

D. Simulator facility design.

E. Meteorological tower replacement design.

F. Firefighting procedures.

G. Pollution control facilities (cost estimate).

II . Environmental licensing interface with agencies and public groups.

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I. Collection and analycia of samples for the radiological (biological and water quality) environmental monitoring program.

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l VEGP-FSAR-13 l 13.1.1.2.2.1 Engineering Services. The manager-engineering and construction services is responsible to the vice president-engineering and construction services. Engineering services is responsible for supplying requested engineering support involving design, procurement, and construction for the company's operating nuclear, fossil, and hydroelectric generating plants.

13.1.1.2.2.2 Engineering. The manager-engineering is responsible to the vice president-engineering and construction l

l services. Engineering, comprised of the civil, mechanical, and electrical engineering divisions, is responsible for providing l requested engineering support involving design, procurement, I construction, and implementation of projects related to GPC's l fossil and hydroelectric generating plants, and in nonsafety-related applications to nuclear plants, as requested by GPC's Muclear Operations Department.

13.1.1.2.2.3 Manager-Environmental Affairs. The manager-onvironmental affairs is responsible to the vice president-engineering and construction services. The section is responsible for managing and coordinating GPC's overall environmental program principally for generating plants, to assure compliance with stato and federal environmental regulations in design, construction, and operation of these facilities. Environmental affairs coordinatos and obtains all environmental permits and licenses for generating facilities from the Stato 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, studios, and analyses to ensure that generating facilities comply with environmental regulations. In performing those services, environmental affairs provides an interface for communications with outside agencios regarding environmental .

matters.

13.1.1.2.3 Nuclear Operation Department The nucioar operation department, under the supervision of the senior vico president-nuclear power has the direct responsibility for the operation and maintenance of CPC's nuclear plants. Support may be provided to the nuclear i

operation department by other GPC departments and SCS.

I Technical, engineering, and administrativo personnal of the power generation department general office staff (nix functional units) consists of 21 persons as of January 1, 1984, as follows:

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13.1.1-8 Amand. 16 4/85 i

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l VEGP-FSAR-13 A. The number of graduate degrees: baccalaureate - 21; masters - 5.

j B. The total man-years of nuclear plant experience - 268.

The structure of the general office nuclear power department staff is shown on figure 13.1.1-3 and described in the following paragraphs.

13.1.1.2.3.1 Senior Vice President-Nuclear Power. The senior l

vice president-nuclear power is responsible to the executive vice president-power supply for the safe, reliable, and officient operation, construction, and maintenance of GPC's nuclear plants. He works closely with the other departments and SCS to ensure that the plant design, construction, and operation are carried out officiently and safely, i

! 13.1.1.2.3.2 Senior Vice President-Nuclear Operations. The l senior vice president-nuclear operations is responsible to the

! senior vice president-nuclear power for the safe, reliable, and officient oporation of GPC's nuclear plants.

i 13.1.1.2.3.3 Vice President and Conoral Manager-Nuclear Operations. The vice president and general manager-nuclear operations:in responsible to the senior vice president-nuclear i operation for the safe, reliable, and officient operation of all l nuclear generating plants in the CPC system.

l l 13.1.1.2.3.3.1 Engineering Project Manager. Reporting to the vice president and general manager-nuclear operations, the engineering project manager will be responsible for performing the following functions:

A. Reviewing engineering services by analyzing project -

requirements. The engineering project manager is the nuclear operations corporato interfaco for GPC with i

Bochtel Power Corporation, SCS, and Westinghouse and, as such, ensures that action or response requested by the participants is made by the propor groups with GPC. The engineering project managar koops the vice l president-nuclear operations informed of project status by providing status reports, which indicate problem areas. In addition, ho makes suggestions as l necessary.

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VEGP-FSAR-13 B. Serving as the principal interface between the Vogtle l plant staff and the GPC power supply engineering, l construction, and procurement departments, and/or outside architectural / engineering organizations to ensure coordination.

C. Participating with the Vogtle plant staff in reviewing l

and approving engineering designs, cost estimates, and specifications to ensure that they are responsive to project requirements and in compliance with established company guidelines.

l D. Monitoring project engineering, procuromont, and l construction progress to ensure that project schedules i are mot and to ensure that budget and cash flow l requirements are met.

13.1.1.2.3.3.2 Manager-Nuclear Engincoring and Chief Nuclear Engineer. The manager-nuclear engincoring and chief nucle _

engineer reports directly to the vice president and general ,

manager-nuclear operations. As manager of the nuclear division, the manager-nuclear engineering and chief nuclear engineer in responsible for:

A. Providing regulatory and licensing support for the operating nuclear units.

B. Documenting licensing contacts with the U.S. Nuclear l Regulatory Commission (NRC) and maintaining files of all NRC correspondence.

C. Interfacing with the appropriato companies and organizations in the areas of nuclear fuel management, procuromont, and reproconsing.

D. Evaluating and preparing amendments to the plant operating licenses and FSARs for operating nuclear units.

E. Preparing and maintaining plant security plans.

F. Addressing safety evaluations and unroviewed safoty questions for design changen to operating units.

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VEGP-FSAR-13 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.

13.1.1.2.3.3.2.1 The manager-nuclear regulatory engineering reports to the manager-nuclear engineering and chief nuclear engineer and is responsible for providing plant support in the areas of licensing, NRC compliance, legal considerations, and fuel management.

The manager-nuclear regulatory engineering is responsible for maintaining the operating licenses, Technical Specifications, Environmental Technical Specifications, 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 information, 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. Those responsibilition include establishmont and maintenance of a fuel procurement policy and management of the implementation of the established policy.

13.1.1.2.3.3.2.2 The manager-nuclear engincoring 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 engineering, special engineering activities, and plant operations support. This support is .

directed towards ensuring compliance with regulatory requirements associated with backfitting and assurance of safe, efficient plant operations.

13.1.1.2.3.3.2.3 The manager-nucioar oporations analysis reports to the managar-nuclear engineering and chief nuclear l engineer and is responsible for providing support for operating i

nuclear plants in the areas of nuclear plant operations analysis, licensco event report (LER) review, gonoric review, safety evaluation programs, probabilistic risk assessment, and a 3.1.1-11 Amend. 6 4/05

VEGP-ESAR-13 accident analysis. This individual is responsible for conducting reviews of plant maintenance trends, surveillance trends, licensee event reports, and other incidents, and developing solutions to problems in these areas. This individual provides plant support to ensure the applicable guidelines developed by the Institute of Nuclear Power Operations (INPO) are utilized.

In the area of LER review, the nuclear operations analysis manager is responsible for development of interpretations and corrective actions concerning personnel errors, component

! failures, and repetitive events. Included in this responsibility is the review of generic events provided by INPO, i

Nuclear Safety Analysis Center (NSAC), NRC, and other outside

! agencies in order to make recommendations for action to be taken by the nuclear plants. The manager-nuclear operations analysis develops trends and analyzes root causes for these events.

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13.1.1.2.3.3.3 Manager-Nuclear Training. The manager of nuclear training reports directly to the vice president and general manager-nuclear operations. The manager-nuclear training is responsible fort l A. Providing the preparation and conduct of training programs at GPC nuclear plants and training centers to ensure compliance with NRC regulations and ensuring l

that the applicable guidelines of the Institute I of Nuclear Power Operations standards are utilized; l ensuring that nuclear operations personnel have the education, training, and skills to safely and efficiently operate and maintain the plants.

B. Administering the utilization of the plant site l

l simulators by both GPC personnel and those from outside

! organizations to maximize the utilization of the simulators. .

l C. Maintaining and 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, l

chemistry, and control and instrument technology.

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VEGP-FSAR-13 E. Ensuring that all training programs and materials are documented to comply with NRC regulations and address INPO criteria.

13.1.1.2.3.3.4 Manager-Nuclear Planning and Control. The manager-nuclear planning and control reports directly to the vice president and general manager-nuclear operations. The manager of nuclear planning and control is responsible for:

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. Providing input into the GPC 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 of exchanging data and information to enhance and improve the safety and efficiency of GPC nuclear operations.

E. Addressing safety evaluations and unreviewed safety questions for design changes to operating units.

F. Providing any other technical, licensing, or nuclear expertise, or onsite technical assistance that may be required.

13.1.1.2.3.3.5 Manager-Nuclear Chemistry and Health Physics.

The manager-nuclear chemistry and health physics reports directly to the vice president and general manager-nuclear operations and is responsible for providing plant support in the areas of emergency preparedness, radiological environmental a_ssessment, health physics, radiation protection, plant chemistry, radwaste, and radiological health safety.

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r VEGP-ESAR-13 In the area of emergency preparedness, this individual has overall responsibility for preparation and maintenance of the Emergency Plan. This includes the development and implementation of emergency drills and exercises; federal, state, and local interfaces; and public information programs.

Additional 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 assessment activities includes following regulatory requirements for radiological environmental monitoring, assessment, and reporting as required by federal regulations, and analysis of routine and unplanned releases of radioactive materials.

In the areas of health physics, radiation protection, plant chemistry, and radwaste, the manager-nuclear chemistry and health physics is responsible for overall support of plant programs, including program upgrades and improvements.

13.1.1.2.3.3.6 Manager-Nuclear Performance. 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:

A. Manage the activities of the nuclear performance department in 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.

B. Track events of safety significance, and such items as nuclear plant capacity factor, plant availability, forced outage rate, and heat rate.

C. Coordinate the nuclear plant reliability data system to ensure full implementation and participation by all operating nuclear plants.

D. Monitor maintenance productivity and performance to develop programs to improve productivity.

E. Develop, direct, and coordinate a nuclear plant >

performance monitoring program to maximize unit

, efficiency and nuclear plant productivity at each nuclear generating facility.

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VEGP-FSAR-13 17.1.1.2.4 Senior Vice President Fossil and Hydro. All fossil and hydro generation plants come under the administrative control of the vice president and general manager-fossil and hydro operations. The fossil and hydro department will provide limited support to VEGP. Any support provided VEGP will be as requested.

13.1.1.3 Quality Assurance Department The vice president and general manager-quality assurance (QA) is responsible functionally to the executive vice president-power supply. The executive vice president has authorized the vice president and general manager-QA to manage 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 composed of a staff in the corporate headquarters 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 site is managed by a QA site manager who reports to the vice president and general manager-QA 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 involved in construction, preoperational testing, and plant operations conform to QA program requirements and approved procedures.

The QA department will not provide technical support (as defined in Section 13.1.1 of Regulatory Guide 1.70) for the operation of VEGP. The activities of the QA organization will be limited to quality assurance functions, which are fully described in section 17.2.

13.1.1.4 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 Nuclear Plant, a nuclear power plant with two boiling water reactors.

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VEGP-FSAR-13 The corporate' organization, which provides the line responsibility for the cperation 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.

4 Members of the corporate headquarters staff available for the

' technical support of the Vogtle Project possess that 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 j health and safety of the public.

.The operating organization for the VEGP is described in j subsection-13.1.2. The company technical support organizations 2

for operation, modification, and maintenance are described in paragraph 13.1.1.2 and shown in figures 13.1.1-2, 13.1.1-3, and 13.1.1.4. The organization described herein provides assurance of safe operation of VEGP Units 1 and Units 2 and for meeting i regulatory requirements. Nevertheless, there are planned increases to strengthen the corporate staff prior to Unit 1 fuel loading.

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The resumos of selected corporate staff members who provide technical support for VEGP are shown in table 13.1.1-1.

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y VEGP-FSAR-13 1 TABLE 13.1.1-1 (SHEET 1 0,F 19)

OFESITE 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 prp.curement 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 j electrical engineer, chief engineer, manager of production, general manager of production, vice president and general manager-power generation, senior vice I president-power generation, and senior vice president- I 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 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 2 OF 19)

George F. Head, senior vice president-fossil and hydro power Responsibility and Authority Responsible to the executive vice president-power supply for the design, construction, and operation of all fossil and hydro generation Educational Background Georgia Institute of Technology B.S., mechanical engineering Professional Experience and Training Georgia Power Company Senior vice president-fossil and hydro power, general office, January 1984 Senior vice president-power generation, general office power generation, May 1981 Vice president and general manager-fossil and hydro generation, general office power generat2on, January 1980 General manager-fossil and hydro generation, general office power generation, November 1979 Deputy general manager-power generation, general office power generation,' January 1978 Deputy general manager-production, general office ,

production, May 1977 Manager-production, general office production, August 1975 Assistant manager-production, general office production, February 1973 Superintendent-production, general office production, July 1969

. Coordinator of engineering and construction for Plant Hatch, September 1968 Production engineer, general office production, July 1968 Amend. 4 2/84 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 3 OF 19)

Assistant superintendent, Plant McDonough/Atkinson l

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 Yatos, March 1956 Assistant plant test engineer, Plant Hammond, March 1955 Richard E. Conway, senior vice president-nucioar power l

Responsibility and Authority I

overall responsibility for the direction and delegation of responsibility to the nuclear construction and nuclear operations organizations to ensure that their designated functions are accomplished in an officient and timely l manner (1984-present)

Educational Background l

Georgia Institute of Technology B.S., mechanical engineering Ilarvard Business School 78th advanced management program .

l Professional Experience and Training l

l Southern Company Services and Georgia Power Company, j Birmingham, Alabama Vice president, 1978-1981 l

Georgia Power Company l . Senior vice president-engincoring, construction, and l project management, 1981-1984 Project general manager, Schoror Project, 1976-1978 l Amend. 4 2/84 j Amand. 16 4/85 l

g .- - _

I i VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 4 OF 19)

Superintendent of generating plant construction, 1969-1976 Project superintendent, Plant Hatch, 1968-1969 Assistant pro' ject superintendent, Plant Branch, 1967-1968

\

! Engineering-construction department, 1963-1967' l

Assistant plant test engineer, Plant Yates, 1961-1963 J. P. O'Reilly, senior vice president nuclear operations Responsibility and Authority Responsible to the nenior vice president-nuclear power for the safe, reliable, and efficient operation of GPC's nuclear plants.

Educational Background B.S., Naval Academy M.S., Rensselaer Polytechnic Institute Professional Experience and Training Career has spanned 30 years of government service, primarily in nuclear technology and its management. Navy career included service aboard destroyers, mine sweepers, and aircraft carriers. Served as reactor control officer of the nuclear carrier USS Enterprise during its construction, testing, and initial operation, and also served as executive officer of the Naval Reactor Facility at the National Reactor Testing Station in Idaho. -

Joined the Atomic Energy Commission (AEC) in 1962, served as' chief of the AEC reactor inspection branch in Washington.

In 1971, named head of Region I, which has jurisdiction over nuclear regulatory activities in 11 northeastern states and the District of Columbia.

l In 1977, named head of Region II, which encompasses 10 l .

southeastern states as well as Puerto Rico and the Virgin l Islands.

l Amend. 4 2/84 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 5 OF 19)

Paul D. Rice, vice president and general manager-quality assurance Responsibility and Authority Responsible for defining and managing the implementation of l a comprehensive quality assurance (QA) program for the l company Educational Background Vanderbilt University B.S., mechanical engineering Professional Experience and Training Georgia Power Company (since 1982)

General manager of quality assurance and radiological health and safety U.S. Navy ,

commenced nuclear carcar in 1957 in the Navy nuclear program; hold various management positions in the program including 10 years in the senior overnight position at major privato and Navy sitos where naval reactor plants woro constructed and overhauled; han 22 years experience in the nuclear field Jonso T. Dockham, Jr., vice prooident and general manager-nuclear generation Rooponsibility and Authority l Rosponalble for the nato and reliable operation of the operating nuclear unito; ronponsible for directing the operation of the unita, providing the liconning support, and providing the corporato guidance and control for l

those unitn; during the construction phano at VEGP, i responalble for ensuring that the neconsary proceduros

(

l l

Amend. 4 2/84 Amon1. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 6 OF 19) and startup activities are progressing, along with providing the initial qualified operating staff for the plant Educational Background Georgia Institute of Technology B.S., chemical engineering Regiatored professional engincor, mechanical engineering t Harvard Graduato Businons School Advanced management program Professional Experience and Training Georgia Power Company Manager of nuclear generation and deputy to the vice president and general manager-nuclear generation, May 1980-June 1981 Plant manager, Plant Vogtle October 1977-May 1980 1

Plant managor, Plant Har11ee Branch, December

1975-october 1977 Annistant plant superintendent, Plant Hatch, November l 1970-December 1975 Annistant production ongineer, general offico July l 1969-November 1970 Plant resulta engincor, Plant Arkwright, June 1968-July 1969

! Plant test ongineer, Plant liar 11oo Branch, August 1967-Juno 1968 Plant tout engincor, Plant Arkwright, August 1964-August 1967 ,

1 Amend. 4 2/84 Amend. 16 4/85

r - - -- - - - - - - -- - ~ - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - -

s.

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 7 OF 19)

Assistant plant test engineer, Plant Arkwright, August 1963-August 1964 Army chemical corps exhibit officer Additional Training

-Trained as and held a senior reactor operators license on Georgia Power Company's boiling water reactor, Plant Hatch Currently maintaining a boiling water reactor

• certification by attending simulator training yearly at Plant Hatch Southesastern Electric Exchange \

Public Utilities Management Development Course Emory University Management Program Westinghouse and General Physics ,

Pressurized water reactor training courses Jack C. Causey, vice president-fossil and hydro operation Responsibility and Authority Responsible for the management of.all of the fossil and hydro generating plants' Educational Background Georgia Institute of Technology .

B.S., electrical engineering Professional Experience and Training Georgia Power Company (since 1952)

Manager-power generation 1

Manager-power generation services -

Manager-production services Superintendent of production t Assistant superintendent of production' Amend. 4 2/84 Amend. 16 4/85-

_ _ _ _ _ _ _ _ _ - - . _ _ _ . _ _ . _ . _ _ _ _ - _ _ _ _ _ . . m__...___ _____._____________...________.__________.__...__.._.__._____.____._....______.____.___.__._____...__.____m. -

E VEGP-FSAR-13 i

TABLE 13.1.1-1-(SHEET 8 OF 19) f Test engineer Tester 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 management (May 1981-present)

Chairman-safety review board, October 1980-June 1982 Educational Background Auburn University B.S., electrical engineering Professional Experience and Training

( Georgia Power Company l 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 i 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 g the same submarines from the position of deputy squadron

commander, having direct responsibility for these eight l submarines, December 1955-December 1958 and October

! 1961-May 1978 Additional. Training

~

Simulator training, Sequoyah Nuclear Plant Senior reactor operator Amend. 4 2/84 Amend.'16 4/85 u__._________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _

i s

EGP-FSAR-13 TABLE 13.1.1-1 (SHEET 9 OF 19)

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 i

Auburn University B.S., mechanical engineering Professional Experience,and Training i s4 s 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

~Assistantpldntsuperintendent,-PlantHatch, January L1971-January 1976 Assistant. plant-superintendent, Plant McDonough-Atkinson .

(fossil),; July 1969-January.1971 Plant results engineer, Plant McDonough-Atkinson, May

~

~1967-July 1969.

Plant results engineer,: Plant McManus, August 1963-April' 1967~

Plant test ~ engineer,EPlant Yates, JuneE1962-August 1963

[ Assistant-plant' test engineer;. Plant McManus, August-

- 1960-June 1962.

Amend. 4> 2/84.

Amend.'16 -4/85 i

4

~ f_

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 10 OF 19)

Assistant plant-test engineer, Plant Arkwright, January 1960-February 1960

_ Additional Training Radiological: monitoring Introduction to nuclear power Basic nuclear fundamentals Boiling water reactor technology Observation training Simulator training Balance of plant Prelicensing. course (Plant 1 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 Professional Experience and Training Georgia Power Company Superintendent-training, .VEGP (senior reactor operator license certified)

General Physics Corporation

-Pressurized water' reactor simulator instructor,' 1980-1981 Amend. 4 2/84.

Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 11 OF 19)

U.S. Navy Senior inspector 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 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 Naval nuclear power plant operational training, DIG prototype, West Milton, New York, 1964-Len T. Gucwa, manager-nuclear engineering and chief nuclear 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)

Amend. 4~ 2/84 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 12 OF 19)

Educational Background University of Tennessee B.S., nuclear engineering Georgia Institute of Technology M.S., nuclear engineering Georgia State Un'iversity M.B.A Professional engineer, State of Georgia Certified senior reactor operator 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 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 Amend. 4 2/84 Amend.- 16' 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 13 OF 19)

Engineer-in-training in engineering, production, and construction 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 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 SSG naval nuclear propulsion power plant prototype Engineering division officer onboard an S5W 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  !

)

l I

l l

Amend. 4 2/84 'l Amend. 16- 4/85' I

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 14 OF 19)

Educational Background Macalester College B.A., physics with minor in mathematics and education 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 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 1980-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 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 Amend. 4 2/84 Amend. 16- 4/85

.. ~ . -. _.

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 15 OF 16)

Professional engineer, mechanical, State of Alabama Senior reactor operator license certified, Plant Hatch Professional Experience and Training Georgia Power Company Nuclear operations analysis manager, June 1983-present Assistant plant manager on loan to the Institute of Nuclear Power-Operation, June 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 Maintenance officers course, February 1970-August 3770 Kenneth M. Gillespie, manager-engineering.and construction .

services Responsibility and Authority .

Responsible for' managing engineering and construction services division of engineering and construction services department ~(August 1984-present)

Educational Background

, , Clemson University B.S.,-mechanical engineering Professional Experience and Training Amend. 4 2/84

' Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 16 OF 19)

Georgia Power Company Manager-engineering services, power supply engineering and services department, December 1981-July 1984.

Construction project manager, VEGP, July _1978-December 1981 4

Project superintendent (construction project manager),

Plant Hatch, October 1974-July 1978 Assistant project superintendent, Plant Hatch, July 1973-l August 1974 Onsite mechanical engineer, Plant Hatch, July 1969-July 1973 Mobile nuclear exhibit manager, Atlanta, June 1968-July 1969 Results engineer, Plant Hammond, March 1967-June 1968 I

Test engineer, Plant Hammond, February 1964-March 1967 i Assistant plant engineer, Plant Arkwright, June 1961-June 1962 U.S. Army January.1962-February 1964 Additional Training 3

Management techniques .

EEOC training Productivity seminar Nuclear power at nuclear utility services-Roy George Davis, manager-engineering, engineering and construction services Educational Background Missouri School of Mines and Metallurgy B.S. chemical engineering Amend. 4 2/84 Amend.-16 4/85-

- ~ w- r

I I

l VEGP-ESAR-13 l

l TABLE 13.1.1-1 (SHEET 17 OF 19) l l Georgia State University i MBA l Professional engineer, civil, i State of Georgia Responsibility and Authority Responsible for directing and coordinating civil, mechanical, and electrical engineering activity for new and existing generating plants and other company-owned facilities to ensure that these plants and facilities meet or exceed industry and professional standards, and that they comply with government regulations and operate in a reliable, safe, and most efficient manner.

Professional Experience and Training

! Project manager recirculation pipe replacement, 1983 - 1984 i

Project construction manager, Rocky Mountain,.1982 - 1983 Assistant to project general manager, Scherer Project, 1980 - 1982 l Manager-schedule support and administration, Wallace Dam, 1979 - 1980 Assistant to project general manager, Scherer Project, 1977 - 1979

Assistant structural engineer, 1974 - 1977

Junior engineer, structural section, 1968 - 1974 I~

W. R. Woodall, Jr., manager-environmetal affairs Responsibility and Authority Responsible for environmental reports for construction

. permits and operating' licenses for. Plant Hatch and VEGP;

! supervises nonradiological environmental monitoring, licensing and compliance.

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

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 18 of 18)

Educational Background University of Georgia B.S., zoology M.S. and Ph.D, entomology Professional Experience and Training Georgia Power Company Manager-environmental affairs, September 1984 - present Power supply laboratories manager, 1980 - 1984 Supervisor, environmental affiars center, 1978 - 1980 Environmental specialist, 1972 - 1978 Additional Training Plant Hatch, badge training program Ronald H. Pinson, vice president-engineering and construction services Responsibility and Authority Responsible for power supply engineering and services department, as well as the services, personnel, labor relations, and safety phases of the construction department (January 1984 - present)

Educational Background .

Auburn University B.S., mechanical engineering Professional Experience and Training Georgia Power Company Vice president and general manager-generating plant construction, July 1981-January 1984

~

General manager-generating plant construction, January 1980-July 1981 Amend. 4 2/84 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.1-1 (SHEET 19 OF 19)

Project general manager, Scherer Project, November 1978-Januaiy:1980 s Manager-generating plant construction, October 1976-November 1978 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 i Assistant' plant test engineer, Plant Hammond, January 1959-February 1961 4

0363V Amend. 4 2/84 Amend. 16 4/85

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PRESIDENT i

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i EXECUTIVE  !

VICE PRESIDENT I POWER SUPPLY

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I I I I NIOR WCE PRESIDENT VICE PRESIDENT SENIOR

& GENERAL MANAGER VICE PRESIDENT ENGINEERING &

VICE PRESIDENT QUALITY ASSURANCE FOSSIL & HYDRO CONSTRUCTION

, NUCLEAR POWER POWER SERVICES I t2393(O$1)

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. .unend. 3 1/84 Amend. 16 4/85 i

CORPORATE ORGANIZATION

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Geo ia Power A EL YCTRlCGENERATINGPLANT UNIT 1 AND UNIT 2 VEGP UNITS 1 AND 2l FIGURE 13.1.1-1 3605-0

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

t EXECUTIVE VICE PRESIDENT ,

POWER SUPPLY ,

VICE PRESIDENT i

ENGINEERING AND I

CONSTRUCTION SERVICES i

I MANAGER OF OF OF ENVIRONMENTAL ENGINEERING AND ENGINEERING AFFAIRS CONSTRUCTION SERVICES x

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CHIEF CHIEF CHIEF MECHANICAL GENERATING PLANT i CIVIL ENGINEER ENGINEER ELECTRICAL ENGINEER

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Amend. 16__4/85 VOCTLE TECHNICAL SUPPORT ORGANIZATION ELECTRIC GENERATING PLANT Georgia Power UNIT 1 AND UMT 2 FIGURE 13.1.1-2 (SHEET 1 OF 2)_

433-9

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FIGURE _13.1.1--2 _(SHEET 2 OF 2) 433-9

l l

VEGP-FSAR-13 l

13.1.2 OPERATING ORGANIZATION 13.1.2.1 Plant Organization The VEGP consists of two nearly identical nuclear gene. sting units. The plant organization applicable when both uaits are operational is shown in figure 13.1.2-1. The plant ataff, excluding the security department, will be manned with approximately 600 full-time employees.

13.1.2.2 Plant Personnel Responsibilities and Authorities 13.1.2.2.1 Overall Plant Management l

l The general manager-Vogtle nuclear operation (GMVNO) is responsible for direct management of the plant, including l

industrial relations, planning, coordination, direction of operation, training, maintenance, refueling, and technical

, activities. The GMVNO is responsible for compliance with the l requirements of the operating license, technical specifications, l and quality assurance program. In the GMVNO's absence, the deputy general manager assumes this responsibility. The GMVNO a 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.)

The GMVNO reports to the manager-nuclear operation in the nuclear operation department. The manager-nuclear operation reports directly to the vice president and general manager-nuclear operation. The GMVNO has access to the advice and services of technical specialists within Georgia Power Company (GPC), Southern Company Services (SCS) nuclear support, and outside expertise as necessary. .

Reporting to the GMVNO directly and indirectly are the following selected positions:

. A. The deputy general manager, along with the GMVNO, who l is responsible for the overall operation and maintenance of the plant.

B. The manager-unit operations, who is responsible for the overall operation and maintenance of the plant.

C. The superintendent-operations, who is responsible for operating the plant safely and efficiently, and who reports to the manager-unit operations.

4/85

, 13.1.2-1 Amend. 16

VEGP-FSAR-13 D. The superintendent-plant engineering and services, who is responsible for onsite engineering and technical support of the plant.

E. The superintendent-maintenance, who is responsible for performance of preventive maintenance and repairs on plant equipment.

F. The health physics superintendent, who directs chemical, radiochemical, and health physics activities, and who is responsible for the radiation protection program of the plant.

G. 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 federal, state, and local regulations.

H. The quality control supervisor, who is responsible for performance of work inspections, verification of procedures used in the control of special processes, and material equipment control of the plant. This supervisor reports to the Superintendent of Regulatory Compliance.

I. The superintendent-administration, who is responsible for developing and implementing office practices which enable correspondence, document control activities, and other general office activities to be accomplished efficiently.

J. 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.

K. 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.

L. The procurement review section (PRS) site supervisor, who is responsible for ensuring that requisitions for parts, materials, and services specify the correct 13.1.2-2 Amend. 16 4/85

VEGP-FSAR-13 procurement level (safety classification). For those requisitions considered safety related, the PRS site supervisor is responsible for ensuring that the appropriate technical and quality requirements are specified. The PRS site supervisor is also responsible for ensuring that documentation received with safety-related parts and materials is adequate.

The work experience and educational background requirements for department heads and selected personnel are described in subsection 13.1.3. The resumes of selected plant staff members are provided in table 13.1.2-1.

13.1.2.2.2 Operations Supervision and Shift Organization The superintendent-operations is responsible to plant management for the operation of the two units of VEGP and shall possess a senior operators license. Each operations supervisor reports to the superintendent-operations. Each operations supervisor shall possess a senior operators license.

The operations supervisor is. responsible for seeing that plant operations are conducted in accordance with appropriate standing orders, plant operating procedures, and technical specifications. The operations supervisor's principal responsibility is ensuring safe plant operation during his assigned shift as addressed in the requirements of item I.A.l.2 of NUREG-0737. The operations supervisor shall possess a senior operators license.

Under the supervision of the operations supervisor, the shift supervisor shall assist the operations supervisor with his duties and responsibilities and shall possess a senior operators license. In addition, he keeps a record of shift activities and '

establishes unit load as directed by the load dispatcher or as emergency conditions dictate. Reporting to the operations supervisor or shift supervisor are the plant operators, assistant plant operators, and plant equipment operators.

The shift technical advisor reports functionally to the operations supervisor and acts to provide both perspective in assessment of plant conditions and evaluation of the safety of the plant. The shift technical advisor reports administratively to the senior shift technical advisor, who reports to the superintendent-operations. The shift technical advisor position meets the intent of NUREG-0660, as clarified by NUREG-0737, item I._A.l.1. The shift technical advisor position may be eliminated if the qualifications of the operations supervisor or shift Amend. 3 1/84 Amend. 7 5/84 13.1.2-3 Amend. 16 4/85

VEGP-FSAR-13 supervisor meet the requirements of the shift tech'nical advisor position. Section 13.2 describes shift technical advisor training, and subsection 13.1.3 describes. shift technical advisor qualifications.

Plant operators and assistant plant operators monitor the plant status and operate. equipment as needed to maintain control of the various plant processes. Most of their duties are located in'the control room, although they may perform inspections in other' areas of the plant. The operating crew may make radiation zand contamination 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 the shift manning requirements for_all modes of operation.

The succession to responsibility for overall operation of the plant and the' authority to issue operating instructions or special orders, in the event of absences, incapacitation of personnel, or other emergencies, shall-be as follows:

A. General manager-Vogtle nuclear operations (GMVNO).

B. Deputy general manager

-C. ' Manager-unit operations.

D. Superintendent-operations.

E. Senior reactor operator-licensed superintendent as designated by GMVNO.

F. Operations supervisor.

G. Shift supervisor.

13.1.2.2.3 Engineering,-Health Physics, Laboratory, and Maintenance Supervision The superintendent-plant engineering and services reports to the initial test program manager-and supervises the engineering staff. Reporting to him are the plant engineering supervisors and a fire protection specialist. (See-subsection 9.5.1 for description of fire protection program.) 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 fqr_ plant operations. The plant engineering supervisors report 13.1.2-4 Amend. 16 ~4/85

VEGP-FSAR-13 to the superintendent-plant engineering and services and aid in his duties and responsibilities. The plant engineering supervisors determine when to call consultants and contractors for dealing with complex problems beyond the scope of available capabilities. This position, therefore, corresponds closely to that identified as " engineer in charge" by ANSI 18.1-1971.

The health physics and chemistry superintendent reports to the manager-unit operations 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. He also ensures that appropriate monitoring devices 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.

The laboratory supervisor-health physics is responsible to the superintendent-health physics and chemistry and will aid the superintendent with his duties.

The laboratory supervisor-chemistry works under the direction of the superintendent-health physics and chemistry and is responsible 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 supervisors, 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 The GMVNO is responsible for the development and implementation of the quality assurance program with the exception of the controls assigned to the quality assurance department (chapter

17) during the initial test phase and operational phase of 13.1.2-5 Amend. 16 4/85 n

}

VEGP-FSAR-13 VEGP. Reporting to the superintendent- regulatory compliance, the quality control supervisor will be responsible for inspection activities required by the quality assurance program.

The vice president and general manager-quality assurance, as described in section 17.2 of the FSAR, is responsible to the executive vice president for managing 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.

13.1.2.2.5 Preoperational and Startup Organization The initial test program manager reports to the deputy 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, delineates personnel qualification, and contains the necessary administrative controls.

The structure of the preoperational and startup organization is shown on figure 13.1.2-2 Reporting to the initial test program manager directly and indirectly are the following selected positions:

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 13.1.2-6 Amend. 16 4/85

m- ,

VEGP-FSAR-13 the schedule supervisor will be schedulers assigned to startup, both Georgia Power Company 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 (CAT) 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 phases of the CAT program. He will utilize primarily maintenance personnel to complete CAT testing.

E. The CAT supervisor is responsible for ensuring that CATS are completed in a timely manner to support the startup summary schedule.

The three CAT supervisors have responsibility. divided according to discipline. The disciplines are electrical, mechanical, and instruments and controls.

The cat supervisors. report to the CAT superintendent. .

Support for completing CATS primarily is from maintenance personnel.

F. The preoperation test superintendent is responsible-for ensuring the development and implementation of preoperational testing program and procedures that are-

.necessary for' controlled and timely. completion ofuthe initial test program. The preoperational test 13.1.2-7 Amend. 16 4/85 L -_____- - ________ -- _ - -__ _ _-- - _-_-____-___ -__--- ___-______-______- _-_-___ _ ____

l VEGP-FSAR-13 superintendent reports to the initial test program l manager.

l The positions reporting to the preoperational test

! superintendent are lead test supervisors, procedures supervisor, and special test supervisor.

G. The special test supervisor is responsible for conducting special tests as described in the startup manual and for directing the individuals providing support for such test activities.

The special test supervisor. reports to the preoperational test superintendent.

H. The procedures supervisor is responsible for the development of and adherence to procedure preparation schedules and administrative requirements.

The procedures supervisor reports to the preoperational test superintendent.

I. The lead test supervisor is responsible for ensuring timely. implementation of preoperational-phase testing i

and turnover activities so as to support initial test

program objectives and milestones.

The lead test supervisor reports to the preoperational test superintendent.

The. lead. test. supervisor provides programmatic and technical assistance and direction to the test supervisors in the performance of turnover and testing activities.

J. The test supervisor is responsible for the conduct of the system turnover and testing activities to support .

the initial test program objectives and milestones.

The test supervisor reports to the lead test i supervisor, K. The hot functional and startup test superintendent is

. responsible for directing the activities associated with flushing, energization, hot functional testing and startup testing. This. position. reports to the initial test program manager.

l 1

13.1.2-8 Amend. 16 4/85

VEGP-ESAR-13 The positions reporting to.the hot functional and startup test superintendent are the energization supervisor, startup test supervisor, hot functional test supervisor, and flushing supervisor.

L. 'The startup test supervisor and hot functional test supervisor are-responsible for conducting the assigned tests and for. directing the individuals providing the support for the test activities.

These positions report to the hot functional and startup test superintendent. They will be supported by plant personnel, contractors, and other Southern system employees in completing their assignments.

M. The flushing supervisor is responsible for the hot functional and startup 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 supervisor reports to the hot functional and startup 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.

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 startup 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 distributions.

'13.1.2-9 Amend. 16 4/85

VEGP-ESAR-13 a

13.1.2.2.5.1 Qualification of Preoperational and Startup Personnel A. Initial Test Program Manager and Program Superintendents Individuals performing these functions shall meet the following. requirements:

1. A bachelor's degree in engineering or related science.

2. Four years experience in responsible positions related to power generation, of which 3 years shall i be nuclear power. '

j B. Lead Test Supervisors, and Preop and Startup Program Supervisors 4

Individuals ~ performing any of these functions shall have as a minimum,

1. A bachelor's degree in engineering or related science and 3 years of power plant experience, or including 2 years nuclear power plant experience,

2. A high school graduate plus 7 years power plant experience, including 4 years nuclear power plant I experience.

C. CAT and Flush Program Supervisors Individuals who perform this function shall meet the following preoperational phase minimum requirements:

I 1. A high school diploma.

2. Four years experience in the craft or discipline he supervises, one year of which shall be nuclear power plant experience.

D.. Test Supervisor (Preoperational Phase)

Individuals performing as test supervisors during the preoperational phase shall satisfy the following

! minimum requirements:

-1. Bachelor's degree in engineering or related '

_ science, and 4.

i 13.1.2-10 Amend. 16 4/85 J

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

i I

l 4 . i t

I VEGP-FSAR-13 (

3 During refueling operations, when the reactor core configuration ,

is being altered, a senior reactor operator will supervise the l fuel handling. activities in the reactor containment. l 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 operations

supervisor is responsible for. implementing the radiation protection program in the absence of the superintendent-health

! physics or his designated alternate.

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f t

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0364V Amend. 3 .

1/84

'13.1.2-12 . Amend. 16 4/85

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VEGP-FSAR-13 i VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 1 OF 73)

RESUMES OF ONSITE SUPERVISORY PERSONNEL George Bockhold, Jr., general manager - nuclear operations Date of Birth: August 31, 1944 Educational Background U.S. Naval Academy, 1966 B.S., power plant engineering Work Experience Nuclear, Georgia Power Company Position: General manager, nuclear operations Vogtle Electric Generating Plant Dates: April 1983 to present Location: Plant Vogtle Plant Status: Construction and startup Job

Description:

Manager of the startup and operation of two ll60-MWe Westinghouse nuclear units. Responsibilities include staffing an organization of over 900 technical and support personnel including contractors, directing the initial plant test program, and safely and efficiently managing the operation and maintenance of these units. These responsibilities include utility assets of 7.2 billion dollars.

Position: Manager, nuclear training Dates: 1981-1983 Location: Atlanta Job

Description:

Managed the initial startup and operation of two Georgia Power Company training centers. Directed the growth of nuclear training to put in service 20 million dollars of training equipment including-a staff change from seven to seventy employees. Training responsibilities included simulator, health physics, maintenance, technician, and general employee training. The training plans were designed to exceed INPO' accreditation and NRC requirements and provide Georgia Power Company with the most professional operations and w n. 9/rs

r s

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 2 OF 72) maintenance personnel for their nuclear ~

plants.

Position: Vice president, General Physics Corporation Dates: 1976 - 1981 Location: Chattanooga, Tennessee Job

Description:

Vice President of the Chattanooga-division responsible for managing and coordinating company efforts in the areas of simulator training, simulator procurement, operator performance research, computer products, and onsite support of utilities startup, maintenance, and operation of power plants. Both the nuclear and fossil Chattanooga groups reported to him. He supervised the Chattanooga division's growth from six to one hundred employees. The Chattanooga division was

. involved with capital projects worth more than 60 million dollars. He also was the project manager of the-following company projects:

Limerick Simulator Managed the procurement of a multimillion' dollar training center which included a boiling water reactor simulator for Philadelphia Electric's Limerick Station. Responsibilities included specification preparation and negotiation with the simulator vendor to obtain fidelity of simulation,- .

flexibility in the computer system, and a training simulator which exceeded NRC requirements and provided excellent manipulation training during all modes of plant operation.

EPRI Simulator Performance Measurement

~ System Directed a research project-which  %

. utilizes the simulator computer system to collect data and objectively evaluate operator-performance. Directed the efforts of the system project group and

~

-several project participants who have x Amend. 16 4/85 'h

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 3 OF 72) expertise associated with selection testing, human factors engineering, and mathematical reliability modeling. This project included both nuclear and fossil simulators.

As director of operations services and manager, training center services, he managed activities associated with on-site support of power plant startup, operations, and maintenance. He directed. General / Physics' use of Browns Ferry and Sequoyah Power Plant Simulators at the Tennessee Valley Authority Power' Production Training Center. Responsibilities included the supervision of the simulator training staff and NRC licensing and requalification programs. He was the supervisor of experienced instructors.

Directed the preparation of and developed BWR and PWR simulator courses and course materials. During this period, he performed detailed investigation of' Browns Ferry and Sequoyah Plant design, construction, and operation to develop control room procedural materials.

Con Edison, New York - Indian Point Station, New' York Position: Nuclear training director Dates: 1975-1976 Job

Description:

Responsible for.all Indian Point training; responsibilities ranged from .

general employee training to licensed operator training and job performance evaluation. Supervisor of. licensed instructors and director of'the' nuclear simulator; simulator responsibilities-included direction-of maintenance personnel to maintain and upgrade system hardware and software, and supervision of simulator training, NRC licensing and  ;

certification programs. Further '

_ responsibilities included the review and pretesting of Unit No. 3'startup '

procedures.  ;

i Amend. 16 4/85 l i

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VEGP-FSAR-13

~

TABLE 13.1.2-1 (SHEET 4 OF 72)

Position: Nuclear simulator director Dates: 1973-1975 Job

Description:

Manager of the simulator project; responsible for the coordination of activities between the contractor, the

. NPC, and Con Edison's departments.

Interface included programs to produce fidelity of simulation and NRC demonstration and certification.

2 Preparation for responsibilities required both formal and informal training associated with computer technology. Director of training for licensed operators and operator candidates utilizing the simulator facility; responsibilities included supervision of instructors, programmers, and maintenance personnel. Instructed

• and directed Unit No. 3 startup crew simulator training to achieve operator licensing on both Units No. 2 and'3.

Position: Production engineer Dates: 1971-1974 Job

Description:

Various maintenance and operations responsibilities for Indian Point Units. Specifically, special' responsibilities included:

1. Licensed shift engineer

, responsibilities during Unit No. 2 startup to.above 20 percent power including unit-testing.

2. Supervision of mechanics and

-operators'during the refueling of Unit-No. 2.

t -3. Maintenance supervision in-high radiation areas during steam generator tube plugging of Unit No. 1.

Other Experience and Training Position: Commissioned Naval Officer Dates: 1970-1971 Location: . -Various with United States Navy Job

Description:

U.S. Naval Nuclear Power School, Bainbridge,. Maryland. Division Director j- Amend. 16 4/85

b

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VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 5 OF 72) of Chemistry, Materials, and Radiological Fundamentals. Instructor of undergraduate college level courses in nuclear engineering systems.

Responsibilities included supervision of instructors and preparation of course material.

Dates: 1968-1970 Job

Description:

USS Simon Bolivar (SSBN 641), a Polaris nuclear powered submarine.

Responsibilities included the following division officer billets - ship's damage control assistant, electrical and .

reactor control officer. -All duties included direction of six to fifteen technicians on operation and maintenance of various equipment, (from air conditioning systems to reactor protection circuitry). Further-responsibilities included implementation of a computer-orientated preventive maintenance system for shipboard equipment. Watchstanding duties included officer-of-the-deck (OOD) and engineering officer-of-the-watch (EOOW). The EOOW is the senior watch officer who is. responsible for the safe operation of'the nuclear power plant, including reactor safety, electrical power generation, and propulsion. The OOD reports directly to the commanding i' officer for the safe navigation and operation of.the ship. l l

Dates: 1966-1968 l Job

Description:

. Navy-specialized training including l

. officer nuclear propulsion and submarine i schools. Qualified EOOW at naval reactor's land-based nuclear' power plant' in Windsor, Connecticut.

Herbert.P. Walker, Manager - unit-operations.

_Date of Birth: June 16, 1942 l

Amend. 16 4/85

i

~

VEGP-FSAR-13

2. One year of power plant experience, or A high school graduate plus 5 years of power plant P

experience, including'2 years of nuclear power

plant experience.

E. Test' Supervisor (Startup Phase) i, Individuals performing as test supervisors during the c startup phase shall satisfy the following minimum .;

~ requirements:

$ 1. ' Bachelor's degree in engineering or related

, . science, and

2. Two years of power plant experience, of.which 1-

syear shall be nuclear plant experience, or j A high school graduate plus 6 years of power plant j

• experience, including'3 years of nuclear power

' plant experience. ,

1 i

! 13.1.2.2.5.1.1 Special Considerations. Individuals who do not possess the formal education requirementsLspecified in paragraph

! 13.1.2.2.5.1 shall not be automatically eliminated.where other-j -factors-provide sufficient demonstration of their abilities.

t The initial test program manager shall evaluate-these persons on j a case-by-case basis and provide documentation of this evaluation in the qualification records, i

f-Completion of formal education beyond'the minimum requirements and formal and on-the-job training may be'used by the' initial .

. test' program manager as partial. satisfaction of experience i requirements, utilizing the guidance of ANSI N18.1-1971, ,

Selection and. Training of Nuclear Power Plant. Personnel.

t 1

13.1.2.3 Operatihg Shift' Crews

, A total manpower in: excess of five' full shift crews is provided-i- .to avoid _. excessive overtime. The minimum number of operation supervisor, shift supervisors,, plant operators,Lassistant plant operators,; equipment operators, and' shift technical advisors are.

shown in table-13.1.2-2. Figures 13.2.1-2 and 13.2.2-1 indicate

! - the' schedule'for senior reactor operator (SRO) and. reactor l - operators (RO) training to meet'the minimum shift steffing and Lother plant-positions.

Amend.. 1/84

13.1.2-11 Amend.'16 .4/85 2

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VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 6 OF 72)

Educational Background Clemson University,14 66 N B.S., electrical engineering Registration: Professional Engineer, State of Georgia Registration No. 11022 Certification: Senior reactor operator (SRO) on Hatch simulator, February 1982 Work Experience Nuclear, Georgia Power Company Position: Manager-unit operations, Vogtle Electric Generating Plant Dates: June 1984 to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Job

Description:

Assists in planning and preparation for startup and operating of VEGP Units 1 and 2. This includes preparation, review, and approval of procedures, plans, programs, and schedules for startup and operation of a two-unit PWR electric generating plant; including preparation of staffing requirements and budgets for the plant.

Position: Assistant plant manager, VEGP Dates: August 1980 to June 1984 Location: General Office, Atlanta, Georgia, and VEGP Job

Description:

Assists in planning and preparation for startup and operation of VEGP Units 1 and 2. This includes preparation, review, and approval of procedures, plans, programs, and schedules for startup and operation of a two-unit PWR electric generating plant; including preparation of staffing requirements and budgets for the plant. .

Position: Project Startup Manager, VEGP

_ Dates: February 1977 to August 1980 Location: General office, Atlanta, Georgia Job

Description:

Plan for and direct activities of startup of VEGP Units 1 and 2. This included, but was not limited to, Amend. 16 4/85

l.

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 7 OF 72) l l preparation, review, and approval of l schedules and procedures necessary for unit startup. Also direct day-to-day activities of employees performing startup activities. Review and approve test results and prepare reports l required by regulations and company j management.

Position: Production engineer Dates: October 1975 to February 1977 Location: . General office, Atlanta, Georgia Job

Description:

Responsible for coordinating licensing activities for Plant Hatch Unit 1. The coordination required contact with the NRC, General Electric, Southern Company Services, and the plant staff.

Primarily, the coordination involved responses to NRC inspection reports, letters, and other documents, and preparation of changes to the unit operating license. During this period the incumbent also served as' safety review board (SRB) chairman. The SRB is

.the corporate independent review and audit group reporting to the responsible company executive. The chairman ensures that the board's functions are completed

~

as required.

Position: Technical supervisor

! Dates: March 1, 1972, to October 1975 Location: Plant Hatch,. Baxley, Georgia-Plant Status: Two nuclear units under construction; later one unit is in operation. .

Job

Description:

Responsible for the test department and reactor engineering. Act in advisory-capacity to various plant supervisors on

, technical matters. Responsible for the technical accuracy of various plant procedures dealing with such items.as instrumentation, fuel handling, and-l maintenance. Assisted in the writing

and review of the Technical l Specifications. Assisted in the writing and performance of the construction l assurance test, both electrical and i

mechanical. Act as coordinator for j writing of preoperational test procedures. Obtained senior reactor Amend. 16 4/85;

_ _ . . - - - - - - - - - - - - - - - - _ _ - _ - - . - - _ - - . . - - - - _ - - - - - _ _ _ . - - . - - u.- - . - -

rn VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 8 OF 72) operators license for Hatch Nuclear Plant Unit 1 in May 1984.

Position: Results engineer Dates: November 1, 1970, to March 1, 1972 Location: Plant Hatch, Baxley, Georgia Plant Status: Two nuclear units under construction.

Job

Description:

Majority of this time spent in training programs. Received operating experience on an operating nuclear reactor while attending a basic nuclear physics course at Georgia Institute of Technology.

Nuclear Training, Georgia Power Company

1. SRO Training - Received 13 weeks of classroom training and 8 weeks of simulator training. The classroom consisted of a review of reactor physics review, thermal hydraulics, health physics, and chemistry.

Additionally, the classroom portion consisted of detailed systems training and plant operations.

2. Introduction to PWR Plant Operation - A 3-day simulator course taught by Westinghouse at the Zion Training Center. The course consisted of simulator instruction in plant normal operations, startup, shutdown, and emergency operations. Various plant ~

transients were observed and correct operations during

'the transient were. demonstrated. Actual hands-on operation of the simulator occurred during this course.

3. Pressurized Water Reactor (PWR) Information Course - A 2-week introduction to PWRs presented by-Westinghouse. The introduction was an overview of-the .

PWR system and operations of systems land the. plant.

The systems were discussed in detail with regard to function, flow rates, and pressure (if appropriate, automatic. activations, trips, and emergency operation).

4. Other Training Taken Prior to Fuel Loading'- A balance-of plant. school covering specific operations of all Hatch nonnuclear systems and prelicensing refresher school covering all Hatch system operations, design criteria, reactor physics, radiation safety, site security, and emergency plans, and plant administrative procedures and controls will be taken.

Will participate in preparing and conducting preoperational test thereby gaining valuable actual operating experience on the Hatch Plant.

Amend. 16~ 4/85 E -___________ __ __ __

F-VEGP-FSAR-13 g TABLE 13.1.2-1 (SHEET }d'OF 72) X:

S. Simulator Training week simulator training course presented by the General Electric training facility near Morris, Illinois, obtaining certification as a senior reactor operator. This training consisted.of both classroom and practical training on the operation i of a BWR under normal, abnormal, and emergency

[ conditions. The simulated reactor was started up and l shut down from various conditions so that.various

j. conditions so that various physical and nuclear phenomena concerning the plant could be observed.

Strict' adherence to procedures and power plant practices was required during operation of the simulator.

Tours of Dresden Units 2 and 3 were also conducted on a regular basis to become familiar with an operating nuclear power plant outside of the control room.

Progress during the course was monitored by use of quizzes,' written and oral examinations, and instructor

-evaluation throughout the course.

l l Final determination for successful completion of the course was made by independent written, oral, and l performance examinations.

6. Observation Training weeks observation training

at Millstone Point Nuclear Power' Station, Waterford, Conn.

l 7. Station Nuclear Engineering - A 10-week course

' . conducted by General Electric at San Jose, California. The course was designed to instruct l

nuclear engineers and technical supervisors in methods of making fuel calculations and applying fuel management procedures to power plant operation.

8. BWR Technology - A 5-week course given.by the General Electric Company at the plant site. This course covered various systems of the plant and,-since the-l instruction was held at the site, provided observation

'of many of the systems during the construction phase.

l 9. Basic Nuclear Fundamentals - A 13-week course at l Georgia Institute of Technology. In addition to the

. 12 startups on the Georgia Tech research reactor (GTRR),-several. power changes and nuclear experiments were performed on the AGN reactor. Several special experiments were conducted in addition to the required startups, power changes, and shutdowns.

Amend. 16 4/85 L - _

VEGP-ESAR-13 TABLE 13.1.2-1 (SHEET 11 OF 72)

10. Basic Math and Physics - A 4-week course covering the fundamentals of mathematics and physics presented by Westinghouse Electric Corporation. This course was designed to prepare the personnel for the type of mathematics and physics normally required for a U.S.

Atomic Energy Commission reactor operator's examination.

11. Introduction to Nuclear Power - A 144-h course by the NUS Corporation covering principals of nuclear physics, reactor thermal characteristics, hydraulic and control characteristics, reactor coolant chemistry, radioactive waste processing, radiation safety, and plant operations.

Nonnuclear, Georgia Power Company Position: Plant test engineer Dates: December 1, 1969, to November 1, 1970 Location: Plant Harliee Branch and Plant Sinclair, Milledgeville, Georgia Plant Status: At Plant Sinclair two (22.5 MW) operating hydro units with supervisory control from Plant Branch. At Plant Branch two (250 MW and 319 MW) operating drum-type fossil units with electrical / pneumatic controls. One (480 MW) operating supercritical type fossil unit with electrical / pneumatic controls with feed-forward electrical signal.

One (490 MW) supercritical type fossil unit under construction and startup (later operating) with turbine EH controls. Also with electrical /

pneumatic controls with feed-forward electrical signal. Both had steam-driven feed pumps. . The EH system was all solid state and both supercritical boilers controls were approximately 50 percent solid state.

Job

Description:

Responsible for testing, calibrating, troubleshooting, and maintaining all plant instrumentation and controls on water treatment plant, boiler, turbine, generator, plant auxiliary equipment.

Test, calibrate, troubleshoot, and maintain all plant instrumentation and controls on water treatment plant.

Amend. 16 4/85 e

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 12 OF 72) ,

Test, set, troubleshoot, and maintain protective relays and protective schemes on generator, main transformer, plant auxiliary equipment, and station service equipment. Troubleshoot and maintain supervisory equipment for Plant Sinclair. Assisted in special tests such as the early valve actuation test.

Position: Assist plant test engineer Dates: April 1, 1968, to December 1, 1969 Location: Plant Harllee Branch and Plant Sinclair, Milledgeville, Georgia Plant Status: At plant Branch two (250 MW and 319 MW) operating drum-type fossil units with electrical / pneumatic controls. One (480 MW) operating supercritical type fossil unit with electrical / pneumatic controls with feed-forward electrical signal. One (490 MW) supercritical type fossil unit under construction and startup (later operating) with turbine EH controls. Also with electrical /

pneumatic controls with feed-forward electrical signal. Both had steam-driven feed pumps. The EH system was all solid state and both supercritical boiler controls were approximately 50 percent solid state.

Job

Description:

Assisted in the maintenance and calibration of instruments and controls for the operational units and in the initial calibration and checkout of these items on the unit undergoing startup.

Position: Senior test engineer Dates: 1967 to April 1968 Location: Relay Test Laboratory, Atlanta, Georgia Position: Junior Engineer Dates: May 1966 to May 1967 Location: Relay Test Laboratory, Atlanta, Georgia Job

Description:

Test and set transformer, bus, and transmission and distribution line

, protective relays. Included pilot wire, carrier, and tone relay schemes. Test and check cts, pts, and potential devices on transformers, circuit breakers, and buses. Test tripping and Amend. 16 _4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 13 OF 72) control circuits for transformers, buses, transmission and distribution lines, and associated equipment. Test

' substation supervisory equipment. Place in service, troubleshoot, and maintain all of the above.

Robert M. Bellamy, initial test manager Date of Birth: March 31, 1951 Educational Background Tennessee Technical University, 1975 B.S., electrical engineering l

Work Experience Nuclear, Georgia Power Company Position: Initial test manager Dates: August 1984 to present Location: Nuclear operations /VEGP Plant Status: Units 1 and 2 under construction Job

Description:

Assumed accountabilities for management of the initial test program, receiving work direction from the project system completion manager and the general manager - nuclear operations.

Accountable for all aspects of the startup testing for both units at VEGP.

Directly responsible for all activities of the engineering staff with responsibility for startup-related activities of all nuclear operation .

departments at VEGP. Primary activities under his direction are: preparation, review, and performance of component tests, preoperational tests, startup tests, and flushing activities; control of programs to efficiently manage test activities and maintain compliance with regulatory requirements; achieve schedule milestones from initial energization through fuel load; development of long-term engineering support for operating phase plant.

Position: Superintendent of plant engineering and services, III Amend. 16 4/85 w - . _ _ . _. _. ._ _ _ . _ _ _ - -- __-- - - - _ - _ _ _ _ - _ - _ .

VEGP-ESAR-13 TABLE 13.1.2-1 (SHEET 14 OF 72)

Dates: July 24, 1981,-to August 1984

~ Location: Power generation /VEGP Plant Status: Units 1 and 2 under construction.

Job

Description:

In this position, responsibilities were a continuation of the previous duties with added budgeting accountabilities and increased staffing requirements.

Initiation of the test program activities resulted in demand for contractors to supplement GPC staff.

Development of test program control testing procedures was paramount among responsibilities,-however, many tasks relating to the development of the long-term operating technical staff were equally prominent.

Position: Plant engineering supervisor

' Dates: March 3, 1979,;to July 24, 1981 Location: Power generation /VEGP Plant Status: Units 1 and 2 under construction.

Job

Description:

Responsible for establishing the engineering department by developing

- organizational plans and by selecting applicants to staff the department. The.

organization grew from one to ninety engineers during this period. Tasks related to the development of supervisors and engineers in_all areas of expertise were~ included in my accountabilities. Other departments did not exist during most of this period resulting in a wide array of staff responsibilities, such as,' reviewing plant design'for operability .

considerations; _ participating in development of project control programs such as work planning and' records management; and ' developing plans, hf procedures,tand' programs relating to the initial test. program.

Position: Plant 1 engineering supervisor Dates: August 26, 1978, to March 3, 1979

- Location: Power generation / Plant Hatch,.

. Plant Status: Both plants operational.

Job

Description:

Primarily responsible for establishment of the balance of plant engineering

~

group consisting of 12 to 15 engineers; technical. direction of these engineers Amend. 16 4/85

___m___._______.__'__[______.m_1_____m_._._._____._________._._.m_..-.-____._m___m__..____.____.m__._ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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TABLE 13.1.2-1 (SHEET 15 OF 72)

I in evaluating system performance against applicable power generation and design

critoria; review and approve all design L- modifications on BOP systems; total

! administrative responsibility for the ,

group engineering; total responsibility ,

to plant management on the balance of plant systems on both nuclear units l

(over 150 systems); analysis of NRC and 's QA requirements for implementation of design changes and generation of a method for implementation; and nonlicense training of group engineers.

Position: Plant engineer Dates: . February 1978, to June 1978 Location: Power generation / Plant Hatch Plant Status: Unit 1 - operational.

Unit 2 - under construction /startup.

Job

Description:

As preoperational test director responsibilities included total responsibility for 33 test engineers in performance and completion of 96 i

preoperational tests; review and approve test results against system design criteria; review and approve.all design changes to plant systems (average of over 100 per month); responsibility'for

. receipt, inspection, and loading of initial fuel load; responsibility for L answers to NRC questions;on system design and power generation criteria; l administrative responsibility for 21 l company engineers; responsibility to the

! plant review board for all documentation .

l verifying testing activities on all plant systems;'and assurance that all commitments for fuel loading activities were met. l Position: Associate engineer Dates: September 1976 to February 1978 Location: Power generation / Plant ~ Hatch Plant Status: Unit operational.

Unit 2 - under construction /startup.

' _ Job

Description:

Work assignments involved: As-

.preoperational test group leader,

! coordination of 46 scheduled system tests; review and approval of test results; review and approval of system l-Amend. 16 4/85 i

i k _'

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 16 OF 72) design changes; generation of some system design changes; analysis of FSARs design commitments to ensure qualifications for receipt of license; direct supervision of 12 test engineers; and responsibility to plant management for all planning / scheduling activities.

Position: Assistant plant test engineer Dates: March 1975 to September 1976 Location: Power generation / Plant Hatch Plant Status: Unit 1 - operational.

Unit 2 - under construction /startup.

Job

Description:

Duties included establishment of a spare parts program including review of all nuclear systems components for parts requirements; review of system piping and instrument drawings and generation of System Flushing Procedures; review of system elementary and wiring drawings and review of system preoperational testing procedures; generation of ESAR sections and preoperational test acceptance criteria on certain test from design parameters; supervision and coordination of component and system testing against design criteria on all plant electrical systems (230 kV, 4160-V ac, 600-V ac, 480-V ac, 120/240-V ac, 120/208-V ac, 125/250-V de, and 24/48-V dc).

Training, Nuclear Course

Title:

SRO Certification Training Dates: March 1, 1983, to July 1, 1983 Course Duration: 680 h

Description:

17 weeks of VEGP-specific training on systems and theory, including simulator training.

Course

Title:

PWR Technology Dates: October 10, 1980 to October 17, 1980 Course Duration: 80 h

Description:

Pressurized water reactor technology

, training.

Course

Title:

Boiling Water Reactor Technology Course Dates: 1978 Course Duration: 480 h Amend. 16 4/85 m.

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 17 OF 72)

Description:

12-week course on Plant Hatch systems and theory.

Training, Other Course

Title:

Managerial Problem Solving Dates: December 6, 1981 to December 11, 1981 Course Duration: 40 h

Description:

1-week course on problem solving techniques.

Course

Title:

P.U.R. Guide Dates: June 1981 to August 1981 Course Duration: approximately 320 h

Description:

Economics and regulatory aspects of public utility operation.

Course

Title:

Foundations of Management Dates: December 14, 1980 to December 19, 1980 Course Duration: 40 h

Description:

1-week course on managerial functions.

Course

Title:

Introduction to Supervision Dates: February 11, 1979 to February 16, 1979 Course Duration: 40 h

Description:

1-week course on leadership and communications skills development.

Candler Clifford Miller, Jr., superintendent of plant engineering and services Date of Birth: May 15, 1952 Educational Background Georgia Institute of Technology Bachelor of electrical engineering Work Experience Nuclear, Georgia Power Company Position: Superintendent of plant engineering and services Dates: September 1984 to present

. Location: Vogtle Electric Generating Plant,

.Waynesboro, Georgia Plant Status: Construction Job

Description:

Direct activities of five engineering supervisors and twenty-two engineers in the areas of fire protection, ASME Amend. 16 4/85 w _. _ _ _ _ . _ __- _

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 18 OF 72)

Section XI programs, computers, electrical technical support, instrumentation, reactor engineering, and cost and scheduling Position: Plant engineering supervisor Dates: July 1982 to September 1984 Location: VEGP site 4

Plant Status: Construction Job

Description:

Supervise two to six engineers in engineering planning section, and two clerks and supervisor in document control. Serve as acting Superintendent

of plant engineering and services.

Position: Senior plant engineer Dates: November 24, 1980 to July 10, 1982

] Location: VEGP site Plant Status: Construction 3

Job

Description:

Supervise two to eleven engineers in

technical support section.

1 Position: Junior plant engineer Dates: September 1975 to March 1977 Location: Plant Hatch Plant Status: Unit I - Operating 3 commercial; Unit II - Pre-Op Test Job

Description:

Technical staff member on Unit I.

Electrical pre-op test supervisor on j Unit II.

i Nonnuclear, Georgia Power Company Position: Commercial engineer, Georgia Power Company -

Dates: September 1978 to November 1980 Location: Statesboro district Plant Status:

Job

Description:

Commercial customer account maintenance coordination, bill calculation, economic evaluation.

Position: Associate engineer Dates: March-1977 to September 1978' Location: Augusta district office

. Plant Status: Electrical distribution. system. Design I construction, and operation.

Job

Description:

Primary customer interface on new l construction. Design of new and rebuilt'

! facilities. Troubleshooting /on-call after hours.

Amend. 16 4/85

_______f.___________._____._______________'

VEGP-ESAR-13 TABLE 13.1.2-1 (SHEET Jd'OF 72)

Nonnuclear, Other Position: Adjunct instructor Dates: Spring 1979, spring 1980 Location: Georgia Southern College Division of Industrial Technology Job

Description:

Junior level courses in lighting design and electrical systems design.

Nuclear Training Course

Title:

Boiling Water Reactor Technology / Plant Hatch Dates: Winter 1976 to 1977 Course Duration: 10 - 11 weeks Vendor: Georgia Power Company In-house, Dan Moore

Description:

Basic course in boiling water reactors and plant auxiliary systems.

Nonnuclear Training Course

Title:

Interpersonal Relationships Dates: October 18, 1982 to October 22, 1982 Course Duration: 40 h Vendor: Georgia Power Company

Description:

Behavioral style awareness, versatility, values, working with other styles.

Course

Title:

New Supervisory Course Date: July 19, 1982, to July 23, 1982 Cource Duratien: 40 h Vendor: Georgia Power Company

Description:

Information on company policies and procedures and on information sources.

Supervisory skills and job expectations.

Course

Title:

Leadership School Dates: May 18, 1981, to May 22, 1981 Course Duration: 40 h Vendor: Georgia Power Company in-house

Description:

Course in communication techniques and interpersonal interaction for personnel with supervisory abilities.

, Course

Title:

Problem Solving & Decision Making Dates: February 1, 1982, to February 3, 1982 Course Duration: 24 h Vendor: Georgia Power Company in-house

Description:

Quantitative solutions to qualitative matters.

Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 22 OF 72)

Course

Title:

Operating School Dates: Fall 1977 L

Course Duration: 10 to 11 weeks Vendor: Georgia Power Company in-house

Description:

Course on design, construction, j

operation, and maintenance of Georgia l Power Company distribution,

! transmission, and substation l facilities.

Melvin A. Griffis, superintendent of maintenance Date of Birth: September 12, 1951 Educational Background Georgia Institute of Technology, 1973 Bachelor of electric engineering Work Experience Nuclear, Georgia Power Company Position: Superintendent of maintenance Dates: August 1983 to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Plant Status: ITP Job

Description:

Organize,and direct maintenance for the preparation of startup.

Position: Plant engineering supervisor l Dates: April 1981 to July 1983 Location: Plant Hatch Plant Status: Commercial operation- .

Job

Description:

Responsible for Torus Modification site coordination and maintenance engineering.

Position: I & C Supervisor j Dates: 1976 to 1981

! Location: Plant Hatch i Plant Status: -Unit.2 startup and Unit 1 commercial i operation l Job

Description:

Responsible for'the construction

. acceptance testing' program of Unit 2 and the maintenance and-surveillance of both units while operating.

Amend. 16 4/85 l

l

f VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 23 OF 72)

Position: Instrument engineer Dates: 1975 Location: Plant Hatch Plant Status: Unit 2 Construction Job

Description:

Responsible for the installation of instrumentation during Unit 2 construction Position: Test engineer Dates: 1974 to 1975 Location: Plant Hatch j Plant Status: Startup Test Program Job

Description:

Responsible for the direction of the I&C department maintenance, surveillance, and startup testing.

Position: Assistant Test Engineer Dates: 1973 to 1974 Location: Plant Hatch Plant Status: ITP and Startup Job

Description:

Responsible for writing procedures, ordering spare parts, setting up surveillance program, and supervision of I&C personnel.

Position: Superintendent of Engineering Dates: July 1982 to August 1983 Location: Plant Hammond Plant Status: Commercial operation Job

Description:

Responsible for training, procedures, and plant engineering Training, Nuclear Course

Title:

Senior reactor operator (SRO) .

certification Dates: January to June 1984, December to June 1985 Cource Duration: 1400 h Vendor: Georgia Power Company Course

Title:

Reactor physics - Shiffer Dates: January to March 1975 Course Duration: 400 h Vendor: Georgia Power Company

Description:

The study of heat transfer within a boiling water reactor Amend. 16 4/85

( - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 24 OF 72)

Course

Title:

Mini-boiling water reactor Dates: 1978 Course Duration: I week Vendor: General Physics 9 Course

Title:

Loose Parts Monitoring Dates: 1978

[ Course' Duration: 4 days Rockwell' International Vendor: '

1 Course

Title:

Principles of Instrumentation Dates: 1975

Course' Duration

2 weeks Vendor: General Electric 1

Other f'

Course

Title:

Human Resources Dates: 1982

, Course Duration: 2 days Vendor: Georgia Power Company Course

Title:

New Supervisor School Dates: 1976 Course Duration: I week Vendor: Georgia Power Company i

Course

Title:

Middle Management Development Basic

! Dates: 1976 Course Duration: 1 week ly Vendor: Georgia Power Company Course

Title:

Critical Path Method School

! Dates: 1979 Course Duration: 3 days Vendor: Georgia Power Company i

Course

Title:

Nilsson Technical Communications  !

Dates: 1983 Course Duration: 2 weeks l

Vendor

. Georgia Power Company Joseph Frank D'Amico, superintendent of regulatory compliance Date of Birth: September 27, 1935

~

Educational Background University of Tennessee, Knoxville, 1970 B.S., Nuclear engineering 4 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 25 OF 72)

Work Experience Nuclear, Georgia Power Company Position: Superintendent of regulatory compliance Dates: August 6, 1983 to present Location: Vogtle Electric Generating Plant.

Plant Status: Beginning initial testing Job

Description:

Provide Georgia Power Company input to FSAR development, Technical Specifications' development, and Operating License Stage Environmental Report (OLSER). Develop and maintain the commitment tracking program, equipment problem tracking program, Technical Specification surveillance tracking program and manage the operating experience assessment program; chair both the plant review board and the test review board; maintain plant administrative procedures; prepare regulatory compliance and quality control procedures; develop and implement the quality control program and prepare for senior reactor operator licensing; coordinate closure of quality assurance, Institute of Nuclear Power Operations (INPO), and NRC findings; and review, track, and trend deficiency reports.

Position: Plant engineering supervisor Dates: June 12, 1982, to August 5, 1983 Location: VEGP Plant Status: Under construction Job

Description:

Provide GPC input to the emergency responso facility, FSAR and OLSER.

Supervise preparation of the emergency plan, operating procedures, engineering procedures, fuel handling procedures, health physics procedures, emergency operating procedures, and the emergency response procedures. Supervise review of assigned plant manual chapters, flushing procedures, and preoperational

. test procedures; and implementatien of the operations assessment program.

Position: Senior plant engineer Dates: October 6, 1980, to June 11, 1982 Amend. 16 4/85

VEGP-ESAR-13 TABLE 13.1.2-1 (SHEET 26 OF 72)

Location: VEGP Plant Status: Under construction Job

Description:

Review piping and instrument diagrams for operability, maintainability and testability. Coordinate spare parts program including policy QA and storage. Development of operating and maintenance procedures. Procurement, placement, and maintenance of test shop equipment. Power generation facilities at construction site.

Position: Senior quality assurance engineer Date: September 8, 1980, to October 5, 1980 Location: VEGP Plant Status: Under construction Job

Description:

Audit construction activities that were subject to the provisions of the QA program. Review procurement requisitions and construction procedures for QA requirements. Monitored construction activities to show compliance to applicable codes and standards. Conducted audits as lead auditor.

Position: Quality assurance engineer Dates: March 3, 1979, to September 8, 1980 Location: VEGP Plant Status: Under construction Job

Description:

Same as Item No. 2.

Position: Senior QA field representative Dates: August 7, 1978, to March 2, 1979 Location: VEGP Plant Status: Under construction Job

Description:

Same Item No. 2.

Position: Officer-In-Charge Dates: May 1977, to April 1978 Location: Fort Belvoir, Virginia Plant Status: Undergoing decommissioning Job

Description:

Officer in Charge of the US Army's barge-mounted MH-1A nuclear power plant. Responsible for implementing the

, decommissioning plan for the MH-1A nuclear power plant. Developed methods for processing radioactive liquid waste from collection tanks, laundry wastes, and the primary loop. Supervised Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 27 OF 72) radioactive material removal and i decontamination operations to ensure compliance with the federal code, i

regulatory guides, and Army regulations. Approved plans for final l site survey for the decommissioning l site, and preparation of the barge for l tow to drydock, the shipyard, and l long-term storage in the James River l reservo floot. Reviewed and approved i drydock and shipyard specifications.

l Developed facility emergency plans, security plans, and implemented approved l plans. Reviewed special safety analysis reports and technical specifications.

Coordinated decommissioning actions with j the Army Reactor Committee for health and safety, and the Maritime Administration.

l l Position: Project Officer I

Dato: March 1977 to April 1977, June 1976 to December 1976 l Location: Fort Bolvoir, Virginia l Plant Status: Shutdown, undergoing emergency core

cooling system (ECCS) modification

! Job

Description:

Reviewed engineering drawings, nuclear l

power plant modifications, proposed facility emergency plans, security plans, operating plans, quality assurance plans, and associated l proceduros. Helped develop contingency plans for relocating the US Army's

, floating nuclear power plant STURGIS.

l

! Position: Commanding Officer, FNPP STURGIS Dates: December 1976 to March 1977 Location: Voyago from Panama Canal Zone to For i Belvoir, Virginia Plant Status: Shutdown for voyage & ECCS modification l Job

Description:

Responsible for vessel preparation crew l training and delivery of the STURGIS l from the Panama Canal Zone to Fort Belvoir, Virgina. Required to ensure l that all federal and military

. regulations were complied with.

Responsible for repairs as a result of damage caused by extreme weather experience on January 7, 1977 off the coast of North Carolina.

Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 28 OF 72)

Position: Plant cuperintendent Dates: February 1974 to May 1976 Location: Panama Canal Zone Plant Status: Operating Doncription: Responsible for the technical management of the US Army's floating nuclear power plant STURGIS. Responsibilition including supervising the operation, maintenance, safety, and nocurity of the STURGIS. Dution included review of technical manuala, coro physics reports, safety analysis reports, special safety analysis reports, technical specifications, operating proceduros, records, loga, modifications, and nuclear reactor occurrences to ascertain compliance with federal regulatory agencies. Reviewed compliance with imminent requirements. Prooided over qualification boards for senior reactor operators and reactor operators at the MH-1A; supervised a zero power experimont to evaluato prototype control rods. Managed a crow of 65 nuclear power personnol. Performed concurrently duties of radiation protection officer, quality annuranco officer, and property book officer.

Position: Radiation protection officer Job

Description:

Provided managemont supervision for all fuel handling operations (now and spent) to includo refueling, receiving, inspecting, and storing of now fuels storing and shipping of spent fuel, .

irradited control rodo, high level radwanto, and low cpecific activity (LSA) radwanto. Pronidad over qualification boardo for all personnel certified as radioactivo material handlers. Ennured compliance with provisions of byproduct materials licenne. Responsiblo for proper donimetry of personnel and reviewing radiation protection procedures.

~

Position: Quality annurance officer Job

Description:

Responsible for review, update, and implomontation of the Quality Anourance Program for the MH-1A and its compliance Amend. 16 4/85 t

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 29 OF 72) with 10 CFR 50 Appendix B. Proposed changes to the technical manual to improve quality assurance by providing better documentation of compliance with technical specifications and federal regulations. Performed QA inspections of operations, maintenance, and health physics sections of the MH-1A nuclear power plant. Reviewed modification proposals, special tests, and evaluations for quality control and quality assurance. Reviewed records and approved personnel for positions of quality control inspectors. Reviewed and approved / disapproved quality assurance documents and drawings both internal and external to the MH-1A nuclear power plant.

Position: Property book officer Job

Description:

Responsible for developing and implementing procedures for the control and accountability of the entire inventory of the nuclear power plant MH-1A. Developed procedures to ensure QA controls were imposed on all required repair parts and equipment in the plants inventory.

Position: Instrument shop supervisor Dates: June 1973 to November 1973 Location: Panama Canal Zone Plant Status: Operating Job

Description:

Supervised all routing and emergency instrument system maintenance. Reviewed .

all instrument maintenance reports and equipment history records for accuracy.

Acted as calibration coordinator for all plant shops to ensure that all test; measurement, and diagnostic equipment was calibrated as required by regulations. Trained assigned personnel to function as instrument repair technicians for the MH-1A instrument systems. Training included theory,

. operation, maintenance, and calibration of all instrument systems-in the plant..

Position: Senior reactor operator Dates: January 1970 to June 1972 and January 1973 to June 1973 Amend. 16 4/85

_____________________J

l i

l VEGP-FSAR-13 L TABLE 13.1.2-1-(SHEET 30 OF 72) l L Location: Panama Canal Zone Plant Status: Operating Job

Description:

Various assignments of shift supervisor l and control room operator. Supervised the operation and manipulated the controls of the MH-1A nuclear power plant. Duties included teaching plant information classes to prospective reactor operator trainees, training reactor operators, and senior reactor

, operators, and serving as a board member l

for qualification boards for reactor ,

operators, and senior reactor operators. Reviewed proposed. changes to '

reactor operating procedures for functional reliability and participated in developing' administrative procedures. Responsible for ensuring the MH-1A nuclear power plant was operated within the limits of the technical specifications and all' I

surveillance requirements were performed-as required. Responsible for the '

operation and safety of the plant, crew, l general public, and all environmental

[ discharges.

l l Position: Drydocking project officer i Dates: June 1972 to January 1973 Location: Panama Canal Zone Plant Status: Shutdown for drydocking and refueling i Job

Description:

Project manager for the first drydocking i of the floating nuclear power plant

! STURGIS. Developed emergency plans, security plans, and contingency plans .,

for both the towing phase and drydocking phase. Developed plans and procedures for all required inspections.

l Position: Refueling manager. f Dates: October 1974 and April 1976 .

Location: Panama Canal Zone '

Plant Status: Refueling outages

-Job

Description:

Performed duties as plant manager for two refueling outages. Responsible for

, all special nuclear material accountability. Provided direct management supervision for core loading, spent fuel transfer, and preparing spent fuel for shipment.

Amend. 1G 4/85

r I

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 31 OF 72)

Position: Refueling team chief Date: March 1973 Location: Panama Cannal Zone

' Plant Status: Refueling outage Job

Description:

Direction supervision of a refueling

, team. Instructed the team on refueling l technique, use of refueling tools, and sequence of operations. Trained the team in safety requirements and proper response to emergencies.

Position: Refueling team member .

Date: December 1970 Location: Panama Canal Zone Plant Status: Refueling outage Job

Description:

Operated equipment and manipulated controls to refuel the MH-1A pressurized water reactor. Operations included removing reactor vessel head, installing refueling shield tank, installing poison i finger rod assembled to poison the core, refuel the core per established sequence, reassemble the reactor vessel head, and control rod drive assemblies.

Position: Instrumentation Technician Dates: June 1970 to November 70, June 1967 to June 1969 Location: Fort Belvoir, Virginia Job

Description:

Performed duties as instrument technician instrument training instructor and instrument shop supervisor. Developed procedures to document compliance with Technical Specifications, Federal Regulations, and Army Regulations. Taught basic

electronics, math for computers, l radiation detection, portable and nuclear instrument circuits, process instruments, and automatic control

systems.

l Nonnuclear (Other) l Position: Classification inspector Dates: February 1974 to May 1976 Location: Panama Canal Zone

! Job

Description:

Inspected government-owned, power plant equipment and materials for classifying as usable, economically repairable, or Amend. 16 4/85

E l VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 32 OF 72) salvage. Duties were performed i concurrently with duties as plant l

superintendent.

Nuclear Training

! Course

Title:

Nuclear Power Plant Operators Course l

Dates: March 1966 to March 1967 Course Duration: 1 year military school.

l School: US' Army Nuclear Power Program

Description:

Course taught in three 4-month phases:

academic subjects, operations, and specialty. Academic subjects included math,~ physics, water chemistry, mechanical engineering, electrical engineering, nuclear engineering, and health physics. The operations phase consisted of working as a trainee in a nuclear power plant. The equipment operator trainee learned _ equipment operation, system components, system function,_ systems interactions, l turbine-generator operations, containment entry procedures, startup, and shutdown. The' control room operator j trainee was trained on emergency procedure response on the simulator for l the nuclear power plant. The specialty

[ phase consisted of a additional training i

in one area as directed by the school. ,_

i Instrumentation specialty consisted of training in electronics, circuit design, troubleshooting and repair technique, electronic instruments and pneumatic instruments. .

l i Course

Title:

Instrumentation Speciality Course

! Dates: March 1967 to June 1967' '

Course Duration: 4 months military school-School: US Army Nuclear Power Program l

Description:

Instruction included theory of-operation, maintenance, calibration, and repair'of all. plant process instruments,_

i nuclear instrumentation, and radiation monitoring equipment. le l

~ Course

Title:

Radiation Protection Officer Course i Date: April 3, 1974 to April 24, 1974 Course' Duration: 3 weeks, military school i School: U.S. Army, Aberdeen Proving Grounds Amend. 16 4/85 t_

.[I VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 33 OF 72)

Description:

Instruction covered principles of radiation protection, decontamination procedures, control of low levels and high levels waste, management and control of contaminated area, and requirements of code of federal regulations.

Course

Title:

Plant Superintendent General Course Dates: September 1973 to November 1973 Course Duration: 12 weeks, military school School: US Army Nuclear Power Program -

Description:

Course was self study with supervised exams. Topics covered included core physics,. control rod worth, reactivity control, health physics, fuel accountability, engineered safety features, emergency planning, physical security, army regulations, CFR Titles 10, 46 and 49, and Corps of Engineer requirements.

Course

Title:

Plant Superintendent Specific (MH-1A)

Course Date: December 1973 Course Duration: 5 weeks, military school' School: U.S. Army Nuclear Power' Program

Description:

The topics studied in the' general course are covered as they.related to the MH-1A floating nuclear power plant. In addition to Titles 10, 46j and 49 of the 34 CFR, US Coast Guard and Panama Canal Zones were addressed.

Course

Title:

Quality Assurance Seminar .

.Date: June 1975 Course Duration: 1 week Vendor: .

American Society for Quality Control

Description:

Selected topics included QA program development, procurement of replacement parts,'and storage requirements.

Course

Title:

. Auditor Training Dates: November 13, 1978 toLNovember 17, 1978 Course Duration: 40 h

. Vendor: Bechtel Power Corporation

Description:

Basic principles and~ techniques of auditing, preplanning, audit plan, use of checklists, and importance of good communication were topics addressed.

Amend.: 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHECT 34 OF 72)

Course

Title:

Liquid Penetrant Testing Dates: May 1979 Course Duration: 40 h Vendor: s Georgia Power Company, training

,t department

Description:

The course covered various types of penetrants, use of black light, code acceptance criteria, and bands on elevation. Certified Level I Inspection.

Course

Title:

Pressurized Water Reactor (PWR) Systems Dates: '

October 6, 1980 to October 17, 1980 Course Duration: 80 h Vendor: General Physical Corporation

Description:

The course covered system classification for typical pressurized water reactor

! systems.

i Course

Title:

PWR Auxiliary Feedwater System Workshop .

Dates: February 5, 1981 and February 6, 1981 Course Duration: 16 h Vendor: INPO

Description:

The., workshop covered construction, controls and problems with auxiliary feedwater systems for. nuclear plants.

Course

Title:

Hatch Nuclear Plant Radiological Emergency Team (RET) Training.

i Date: May 25, 1982 Course Duration: 8h Vendor: GPC

Description:

The training provided familiarization with the HNP emergency plan and' duties .

and responsibilities of RET members.

Course

Title:

Pressure Thermal Shock (PTS)

Dates: November 17, 1982, to November 19, 1982 Course Duration: 24 h Vendor: Westinghouse Electric-Corporation

Description:

Material properties, fracture mechanics,

-Newton embrittlement, Warm Prestressing, and operations during PTS events were discuqsed. PTS events were demonstrated-using the.: plant simulator.

Course Title': Emergency Response Guidelines (ERG)

Workshop Dates: September'27, 1982, to October 1,'1982.

. Amend. 16 4/85 d

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 35 OF 72)

Course Duration: 40 h Vendor: Westinghouse Owners Group

Description:

The training covered the ERG program development, critical safety functions (CSF), CSF status fees, and CSF restoration guidelines. The background information developed to support the guidelines were discussed.

Course

Title:

SRO Training Dates: February.1983 to January 1984 Course Duration: 23 weeks Vendor: GPC, Training Center

Description:

Selected topics to prepare for NRC instructor certification and eventually SRO licensing on the VEGP. Included was 6 weeks on the VEGP specific simulator.

Course

Title:

Reactor Safety Date: June 1984 Course Duration: 2. weeks Vendor: MIT

Description:

Selected topics by NRC and industry leaders on PWR and BWR reactor safety.

Included was a discussion of TMI cleanup activities.

Course

Title:

'Requalification Program Date: Continuous Course Duration: One week /6 week interval

Description:

Selection topics to maintain NRC instruction certification and prepare candidate for NRC cold license.

Training, Nonnuclear Course

Title:

New Supervisors Course Dates: July 19, 1982, to July 23, 1982

~ Course Duration: 36 h.

~ Vendor: GPC Description': The course addressed principles of superrision, characteristics of good supir isors, methods for handling conflict, and methods for effective communications.

Amend. 16 4/85 L. __ ..-_A ..

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 36 OF 72)

Course

Title:

Technical Communications Dates: May 11, 1982, to May 14, 1982 Course Duration: 40 h Vendor: Neillson

Description:

The. course covered technical writing, writing effective letters and procedures, how to conduct effective briefings and meetings, and provided opportunities to practice the skills, Course

Title:

Labor Relations Workshop Dates: December 1, 1982 to December 3, 1982 -

Course Duration: 24 h Vendor: GPC

Description:

The workshop covered understanding, interpreting, and applying the union contract.

Course

Title:

Foundations of Management Dates: August 15, 1983, to August 19, 1983 Vendor: GPC, training

Description:

Selected topics on how to manage resources to accomplish company goals.

Course

Title:

New Managerial Grid Seminar Dates: October 9, 1983, to October 14, 1983 Vendor: Univer,sity of South Alabama

Description:

Lectures and practical exercises to examine management styles, identify our own management system,'and ways to enhance our effectiveness as managers.

Course

Title:

Upper Management Development Dates: January 28,.1985,.to February 1, 1985 Vendor: GPC, training .

Description:

Selected topics. designed to increase managerial skills and effectiveness.

Certifications: Equipment Operator SM-1 Nuclear: Power Plant Equipment Operator.- MH-1A Floating Nuclear Power Plant-Amend.'16 4/85

?

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 37 OF 72)

Control Room Operator - SM-1 Nuclear Power Plant Control Room Operator - MH-1A Floating Nuclear Power Plant Shift Supervisor - MH-1A Floating Nuclear Power Plant Plant Superintendent General Plant Superintendent - MH-1A Floating Nuclear Power Plant Officer-in-Charge - MH-1A Floating Nuclear Power Plant Quality Assurance Lead Auditor Liquid Penetrant - Level I NRC Instructor Certification for VEGP Professional Registration:

Professional Engineer - State of Georgia NO. yL 12423 ,

Paul David Rushton, superintendent of nuclear training Date of Birth: August 11, 1953 Educational Background

~ University of South Florida, 1974 -

.:B.S., Chemistry

.Rensselaer Technical Institute, 1982 EM.B.A.

Work Experience Nuclear,. Georgia Power Company Position: Superintendent-nuclear. training

. Dates: .

May 28, 1983, to present

. Location: Vogtle Electric. Generating Plant

' Plant Status: Two units under construction Amend. 16 4/85

i l

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 38 OF 72)

Job

Description:

Supervise a staff of approximately 35 personnel in providing operations maintenance, health physics, chemistry, engineering, and other training for nuclear operations personnel in preparation for startup and commercial operation of the VEGP Units 1 and 2.

Ensure compliance with NRC regulations and INPO guidelines to ensure that plant staff personnel are adequately trained and qualified to perform their job.

Implement and manage train;ng programs based on job performance analysis using methods of criterion referenced instruction techniques.

Administration of personnel equipment, materials and contracts with an annual operative budget of approximately 5 million dollars. Obtain and maintain an NRC SRO certification on VEGP.

Position: Supervisor-operations training Dates: April 12, 1982, to May 28, 1983 Location: Plant Hatch Plant Status: Two units operating Job

Description:

Supervise personnel in providing technical operations and simulator ,

training to nuclear plant operating, engineering, and management personnel to ensure compliance with NRC standards, INPO criteria, and to ensure the safe and efficient operation of the plant by providing quality training programs.

Obtained on NRC SRO certification at Hatch Nuclear Plant .

Nuclear - Other Position: Director-nuclear training Dates: March 1980 to March 1982 Location: US Naval Submarine. School, Groton, Connecticut Job

Description:

Supervised a staff of ten instructors providing sixteen separate courses of instruction in naval nuclear power plant theory, operation,; equipment, and maintenance. This position required training of instructors and coordination of student,. instructor, and classroom schedules to provide maximum training benefit for submarine-nuclear plant

-Amend. 16 4/85

7 VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 39 OF 72) operators. New courses were developed and implemented as needs and weaknesses were identified. Guidance and personal tutoring were provided in advanced aspects of nuclear plant operation to naval officers designated to become qualified as chief engineers of nuclear submarines.

Position: Engineering department division officer Dates: April 1977 to March 1980 Location: Poseidon class nuclear ballistic missile submarine USS Benjamin Franklin (SSBN 640)

Job

Description:

Supervised equipment' operation and maintenance, personnel training, and administration for three successive divisions within the engineering department of nuclear submarine.

Directly supervised nuclear power plant operation on shift as a qualified Engineering Officer of the Watch (EOOW). Controlled and established plant conditions; approved plant operation and testing;- responded to plant transients, casualty, and emergency situations;. ensured compliance ,

with approved operating procedures and guidelines.

Training, Nuclear Course

Title:

VEGP SRO certification instruction-Dates: January 9, 1984, to July 12,.1984 Course Duration: Approximately 1000 h Vendor GPC Course

Title:

HNP SRO certification instruction Dates: August 1982 to May 1983 Course Duration: Approximately 1000 h Vendor: GPC Course

Title:

Naval-Nuclear Power Plant Operators refresher course Dates: .

September 1981

, Course Duration: 4 weeks Vendor: Naval Submarine School, Groton, Connecticut

. Amend. 116 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 40 OF 72)

Course

Title:

Operational Water Chemistry and Radiological Controls Dates: January 1982 Course Duration: 2 weeks Vendor: Naval Submarine School, Groton, Connecticut Course

Title:

Prospective Engineer Officer Course Dates: October 1981 to November 1981 Course Duration: 6 Weeks Vendor: Naval Submarine School, Groton, Connecticut Course

Title:

Secondary Analytical Chemistry Dates: January 1982 Course Duration: 1 week Vendor: Naval Submarine School, Groton, Connecticut Course

Title:

Instructional skills and-methods training Dates: April 1980 Course Duration: 15 days Vendor: Naval Submarine School, Groton, Connecticut Course

Title:

Naval Nuclear Prototype Training Dates: January 1976 to June 1976 Cou'rse Duration: 6 months Vendor: Nuclear. Prototype Training Unit, WJndsor Locks, Connecticut Course

Title:

Naval Nuclear Power School

-Dates: January 1976 to June 1976 Course Duration: 6 months Vendor: Nuclear Power School, Orlando, Florida Allen L. Mosbaugh, superintendent of engineering liaison, Date of Birth: August.16, 1948 Educational Background University of Cincinnati, 1971 B.S., chemical engineering

_ University of Cincinnati, 1974 M.S., chemical and-nuclear engineering University of Cincinnati Ph. D.,' chemical and nuclear engineering (in progress)'

~

Amend.l16 4/85 La_

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 41 OF 72)

Work Experience Nuclear, Georgia Power Company Position: Superintendent, engineering liaison Dates: August 1, 1984, to present Location: Vogtle electric generating plant, Waynesboro, Georgia Plant Status: Construction, preoperational phase Job

Description:

Responsible for the development, preparation, conduct, and coordination of the preoperational test program; supervised five groups of test supervisors consisting of about 60 engineers and a program development and procedure writing group consisting of about 30 engineers. The responsibility of the test supervisors under this program includes: preturnover activities such as scoping, walkdowns, procedure reviews turnover reviews and post-turnover activities such as

~

component testing, flushing preop testing, and startup testing.

Nuclear, (Other)

Position: Superintendent'startup Dates: November 17, 1982, to February 13, 1984 Location: Wm. H. Zimmer Nuclear Power ~ Station Plant Status: Construction preoperational phase Job

Description:

Responsible for startup, construction completion, and testing of the station.

In this capacity, assembled and managed a department of 35 system engineers, a .

scheduling group, clerical staff, and a startup construction contractor (Catalytic, Inc.) including about 50 nonmanual personnel and a variable pool of 50-to 100 crafts. Developed and managed the administrative program and procedures to conduct the activities commencing when systems are turned over-from the constructor to the startup organization for preoperational testing,

. flushing, hydrostatic testing, preoperational testing, and power escalation testing'until the time'of commercial declaration.

Amend. 16 4/85 j

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VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 42 OF 72)

Position: Superintendent technical support division Dates: September 14, 1981, to February 13, 1984 Location: Wm. H. Zimmer Nuclear Plant Station Plant Status: Construction /preoperation phase Job

Description:

Responsible for the technical support division.of the nuclear production department consisting of about 25 engineers. In this capacity, assembled and managed a division of groups including reactor engineering, computer ,

engineering,Lreliability engineering, BOP & NSSS systems engineering, and scheduling. The technical support division is responsible for program such as technical specifications, surveillance program, preoperational test program, startup test program, preventative maintenance scheduling, preop test scheduling (using PREMIS),

reliability engineering, nuclear pollution discharge elimination system (NPRDS), and computer support. The computer group functions as the division procurement manager for several computer including PRIME 400, 750, Honeywell 4010 process computer, and various DEC-computers. The technical support division serves as the station engineering support staff and is centered around system engineer assignments. .The technical support division also makes up the backbone of the shift technical advisor program.

The superintendent technical support division serves as a member of the .

station review board and is the designated nuclear fuel' custodian responsible for special nuclear materials ~ (St@4) .

Position: Superintendent technical support division Dates: February 13, 1984, to July 31, 1984 Location: Wm. H. Zimmer Nuclear Power Station Plant Status: Cancelled / converted i Job

Description:

Developed the plan to layout and )

preserve the station. -Procured and  !

supervised the installation of l dehumidification equipment. 1 As nuclear fuel custodian, supervised l packaging and shipment of 560 nuclear j Amend. 16 4/85 a m.

j

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 43 OF 72) fuel bundles of the Zimmer I initial core to Exxon Nuclear.

Position: Test program coordinator Dates: January 19, 1981, to May 1, 1982 Location: Wm. H. Zimmer. Nuclear Power Station Plant Status: Construction /preoperational phase Job

Description:

Responsible for the conduct and coordination of the preoperational test program in all areas: nuclear steam system; balance of plant;-heating, ventilation, and air conditioning; and LRT. Also shift technical advisor candidate.

Position: Staff engineer Dates: August 31, 1978, to January 19, 1981 Location: Wm. H. Zimmer Nuclear Power Station Plant Status: Construction /preoperational phase Job

Description:

Technical staff member with assorted system, flushing and special project responsibilities during.the preoperational test phase. Flushing responsibilities include assignments as flushing engineer coordinating station flushing activities and reviewing completed flushing procedures.

Developed the cleanliness control and flushing program for the station.

Special-projects included: preparation and coordination of high-efficiency particulate air and charcoal filter testing. contract,. evaluation of radwaste volume reduction equipment backfit,_ ,

review and preparation of environmental .

technical specifications (ETS),

evaluation of_ post accident sampling equipment backfitting preparation of station administration directives, shift supervision of new-fuel receipt and inspection.

. Position: Senior engineer .

Dates: September 1977'to July 1978 Location: -Zimmer Nuclear Power Station

_ : Plant Status: Construction /preoperational phase Job

Description:

.Preoperational system engineer for.

radwaste. treatment systems in the

= construction and early preoperational-phases. Prepared and performed-Amend.;16. 4/85:

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 44 OF 72) preoperational test procedures, performed initial system walkdowns, prepared punchlists and ECRs in preparation for turnover and preoperational testing. Prepared flushing procedures and performed initial flushing.

Position: Chemo Nuclear Consultant Engineer Dates: October 1975 to September 1977 Location: Davis Beese Nuclear Power Station Plant Status: Preoperational to 5 percent power Job

Description:

Consultant to station personnel in plant chemistry, cooling water system, high purity water treatment process, radiochemical analysis, environmental technical specifications, national pollution discharge elimination system permit radwaste process equipment, and process radiation monitoring. Test

, leader for preoperational and startup testing from the beginning of the preoperational test phase through fuel load to about 5 percent power. Test-leader in the areas of primary and secondary chemical addition, initial'and

, startup radiochemistry, process sampling, water treatment, and radwaste.

Position: Research engineer Dates: March 1974 to October 1975 Location: Lynchburg Research Center Plant Status: None Job

Description:

Research and development work at the .

Lynchburg Research Center in fuel corrosion deposit (crud) modeling and radioactive crud thickness measurement.

-Conducted mixing modeling studies for B&W makeup tank boron-control calculations. Received spent fuel assembly form Occonee I for complete destructive hot cell examination.

Prepared survey report for corporate recommendations on various chemical

. process techniques for treatment of liquid, gaseous, and solid radioactive waste.

Position: Chemo nuclear consultant engineer Dates: . January 1975 to March 1975 Amend. 16 4/85'

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 45 OF 72)

Location: RanchoeSeco Nuclear Power Station Plant Status: 50 percent to 100 power Job

Description:

Consultant to station personnel during the power escalation and operating phase for plant chemistry, water treatment, and process sampling. B&W liaison for primary and secondary water chemistry requirements, especially in the area of high purity water treatment processes.

Position: Chemo nuclear consultant engineer Dates: December 1974 to January 1975 Location: Three Mile Island Nuclear Power Station Plant Status: 50 percent to 100 percent power Job

Description:

Consultant for condenser leak detection system, high purity water treatment, and.

process sampling during late power escalation and operating phase.

Position: Research assistant Dates: September 1971 to November 1974 Location: University of Cincinnati, Department of Graduate Studies, Cincinnati, Ohio Plant Status: None Job

Description:

Research assistant building and operating test equipment for two-phase fluid flow transient pressure drops study under AEC contract for use in loss of coolant accident analysis. Designed and constructed large two-phase air-water test loop for two-phase flow pattern study under NSF contract.

Training, Nuclear Course

Title:

SRO License training'(classroom portion)

Dates:

Course Duration: 3 weeks Vendor: Perry Simulator, Tulsa, Oklahoma.

Description:

Course

Title:

SRO License training (simulator portion)'

Dates:

Course Duration: 12 weeks

-Vendor: Perry Simulator, Tulsa, Oklahoma

Description:

Course

Title:

SRO license certification Dates: April 1982 Course Duration:

-Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 46 OF 72)

Vendor: General Electric, Tulsa, Oklahoma

Description:

Course

Title:

Zimmer Specific Systems Training j NSSS & BOP Dates:

Course Duration: 7 weeks Vendor:

Description:

Course

Title:

Shift Technical Advisor Academic Training Dates:

Course Duration: 20 credit h

-Vendor: University of Cincinnati, Zimmer Nuclear Power Station

Description:

Course

Title:

Shift Technical Advisor Simulator Training Dates:

Course Duration: 3 weeks Vendor: General Electric Simulator, Morris, Illinois

Description:

Course

Title:

Fundamentals of BWR Operations Dates:

Course Duration: 32 h Vendor: General Electric, Morris, Illinois

Description:

Course

Title:

Zimmer BWR Transient Analysis Dates:

Course Duration: 1 week Vendor: Zimmer Station '

Description:

Course

Title:

Zimmer Emergency Drill Training Dates:

Course Duration: 60 h Vendor: Zimmer Station

Description:

Course

Title:

Loose Parts Monitoring Training Dates:

_ Course. Duration: I week Vendor: Rockwell1 International, Canoga Park, California

Description:

Amend. 16- 4/85

~_. _

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 47 OF 72)

Vincent Joseph Agro, superintendent - plant administration Date of Birth:

Educational Background University of Alabama in_ Birmingham, 1974 B.S., business administration

.Wo*k Experience

Georgia Power Company Position: Superintendent - plant administration Dates: September 1983.to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Job

Description:

Managing the. financial services function which includes capital and O/M budgeting, definitive estimate reconciliations, manhour/ budget tracking, inquiry / bid process / invoice vertification and payroll functions.

Managing the document control function which includes maintenance and distribution of all plant records and data, maintenance and distribution of approved plant procedures, automated e

_ records management system, micrographics and reproduction services. Managing the human resources function which includes the employment process (hiring, testing, interviews, job offers, etc.), resume review, interpretation of-IBEW Contract, union bid. process for covered vacancies .

and grievances. Managing the office administration function which includes employee benefits (insurance, savings-programs, etc.), maintaining all personnel files, receptionist / PBX duties, maintenance and-distribution of stationery and supplies, petty cash activities, and quality circle / problem solving _ teams. Managing the procedure coordination effort to ensure that

_ approximately 2500 are-prepared-(typed, using proper format, grammer, etc.) in a timely manner to meet scheduled time.

frames to. support commercial operations. Provide work direction to Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 48 OF 72) safety and health advisor onsite who is responsible for continuous walkdowns to ensure compliance with. OSHA standards and regulations, conducting safety awareness training and presenting monthly safety meeting for all personnel.

Position: Site Human Resources Supervisor Dates: September 1980 to September 1983 Location: VEGP Job

Description:

Supervised the personnel / employment functions for 900 construction department personnel which included the complete employment process (hiring, testing, interviews, job offers, affirmative action reporting, etc.)

annual reviews, salary administration, employee concerns, EEOC matters and administration of employee benefits (insurance claims, savings programs, educational assistance, etc.).

Supervised the payroll timekeeping function for 900 construction department personnel on multishift operations.which included posting daily attendance information, tracking all lost time data (personal illness, sickness in family, etc.), processing biweekly reports and distribution of pay checks. Supervised the skills development training group which was primarily responsible for training quality control personnel (250-300) in order to qualify.them for certification /recertification in specific areas of inspection work in compliance with company standards. NRC and ANSI regulations and requirements.

(Approximately 2 years until responsibility was transferred from construction department to the skills development department.)

Position: Senior Construction Analyst Dates: June 1980 to August 1980 Location: VEGP Job

Description:

Administration of the following cost plus and/or unit price contracts: Walsh (prime civil contractor), Ingalls (turbine building steel), AMC (coatings facility), and soils and materials.

Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 49 OF 72)

Provide _ work direction to personnel for verification of contractor invoices to ensure.that reimbursements adhere-to contracts, purchase orders, project agreements, and established procedural terms.

Position: Project administration supervisor, Vogtle Dates: November 1976 to May 1980 Location:

Job

Description:

Development, implementation and maintenance of all project procedures for Southern Company Services.

Establish and oversee the maintenance of a central project file system.

Provide project. direction to document control personnel for. receiving and issuing supplier and domestic drawings, records, data, etc. Coordinate Southern Company Services' administrative efforts as required with other project entities l(projects management, engineering, cost / schedule, licensing, procurement, quality assurance, etc.); appropriate-counterparts at GPC-Atlanta, jobsite and Bechtel: Power Corporation, Los' Angeles.

Function as a centralized information center for: project. personnel as to the current status of project activities.

Coordinate all input from project . .

entities in order to compile, print, and issue the official. project monthly progress report.

A Position: Designer II electrical' design section=

' Dates: October 1967 October.1976-Location:

Job

Description:

Prepare detail-design drawings to ensure compliance with. electrical design'

= criteria:and specifications. Establish

' drawing schedule requirements.toisupport construction schedule need dates.

Review and-approve supplier. drawings to-ensure conformance to design-

. specifications. Supervision of drafters to produceidrawings.

d'yn% 00mpp

&usN -

. Position: ' Drafter, electrical; design.

Dates: '1965 - 1967- <

1 Amend. 16: 4/85

.~ ,

l l

l l

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 50 OF 72)

Location: Rust Engineering Job

Description:

William F. Kitchens, operations superintendent Date of Birth: January 31, 1952 Educational Background

' Georgia. Institute of Technology, 1974 Bachelor of engineering science t

University of Viryinua, 1975 Master of engineering (nuclear)

Work Experience Georgia Power Company Position: Operations superintendent Dates: August 12, 1983, to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Plant Status: Under construction and startup Job

Description:

Responsible for safe and efficient operation of the plant during initial test program and commercial operation.

Direct preparation of operating procedures, startup and hot functional test procedures, and review of security procedures. Responsible for development of qualified operations. staff including employment, training, work planning.

-Also manage buildings and grounds maintenance.

Position: Plant engineering supervisor Dates: April 18, 1981, to August 12, 1983 Location: VEGP Plant Status: Under design and construction Job

Description:

Responsible for development of a qualified engineering staff and implementation of plant procedures manual, fire protection program,-

inservice inspection program,- spare parts program, final safety analysis report, environmental report, security plan, Technical Specifications,.

emergency plan, etc.; performance of.

operational reviews of design documents; preparation of startup summary schedule Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 51 OF 72) and input to Startup Program. Managed staff of over 80 engineers.

Position: Nonlicensed operation (during employee strike)

Dates: July 8, 1981, to July 27, 1981 Location: ~

Plant Hatch Plant Status: Fuell power operation, Units 1 and 2 Job

Description:

Operated equipment, made valve alignments, operated controls, completed paperwork, to process liquid and solid radwaste.

Position: Senior plant engineer Dates: July 28, 1979, to April 18, 1981 Location: Vogtle Project, General Office, Atlanta Plant Status: VEGP under design and construction Job

Description:

Perform design reviews; coordinate final

~' safety analysis report and environmental report reviews, develop plans for inservice inspection program; assist plant management in manpower planning, personnel recruitment,.and training.

Supervised engineers in general office.

Position: Plant engineer,

. Dates: February 5, 1979, to July 27,;1979 Location: Plant Hatch.

Plant Status: Unit I was in commercial operation in various operational. modes, and Unit 2 was in power ascension stage-of startup testing with various operational modes.

Job

Description:

Responsible for technical support for-operation, maintenance, and testing of

.the liquid and solid radwaste systems. .

Performed logic sequence functional

. testing for safety related. control systems.

Nuclear, other Position: Plant engineer

~ Dates: January 2, 1978, to January 26, 1979

. Location: St. Lucie Plant technical staff, Ft.

Pierce, Flordia Plant Status: Unit 1 in commercial operation in various-modes including full power and refueling. . Experienced loss of offsite power and~ natural circulation cooldown.

Unit 2 under construction.

Amend. 16~ 4/85 I

a - - . _ - - - - -

__ a

r-i VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 52 OF 72)

Job

Description:

Provided technical support for operation of Unit 1, including onshift support.

Responsible for equipment performance 4 testing and evaluation; coordinated preparation and review of plant operating, maintenance, surveillance, and administrative procedures.

Alternate member of facility review group. Assisted in coordination and performance of first refueling outage, including return to power. Participated in onshift activities during a planned shutdown from power to establishment of shutdown cooling. Also participated in post-refueling startup testing and subsequent plant startup.

Position: Field engineer

. Dats: January 5, 1976,.to January 1, 1978-Location: St. Lucie Plant, Ft. Pierce, Florida

-Plant Status: Unit--1 in preoperational testing, startup testing, initial-fuel loading, and variou's operational modes, including fuel loading and various operational modes, including full power. Unit 2 under construction.

Job

Description:

Assigned to engineering field office; provided engineering support for construction, startup, operation, and maintenance; prepared safety.

. evaluations, drawings, specifications, and procedures for design changes; dispositioned NCRs and field reports.

Coordinated.a fuel reconstitution effort. . Resolved many equipment related operational problems.

Position: Assistant engineer .

Dates: August 1974 to January 1975 and May 1975 to September 1975 Location: VEPCO General Office, Richmond, Virginia Plant Status: Surry Units 1 and 2 in commercial operation; Surry Units 3 and 4 in conceptual ~ design stage;.

North Anna Units 1 through 4 under construction Job

Description:

Assigned.to licensing section, then-power station engineering section under Co-op program with UVA. Duties involved 4/85 Amend. 16 T 1 '

W k

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 53 OF 72) design reviews and licensing.

Participated in Surry Units 3 and 4 construction permit hearings.

Training, nuclear Course

Title:

PWR Information Course Dates: October 29, 1979, to November 9, 1979, Pittsburgh, Pennsylvania Course Duration: 80 h Vendor: Westinghouse Electric Corporation

Description:

General description of design, operation, and maintenance of a four-loop Westinghouse pressurized water reactor power plant. Emphasis was on NSSS components and control systems.

Course

Title:

Nuclear Power Educational Seminar Dates: April 21, 1980, to April 24, 1980 San Antonio, Texas Course Duration: 32 Vendor: Southwest Research Institute

Description:

Tenth annual seminar on inservice inspection techniques and quality assurance methods for nuclear power plants.

Course

Title:

PWR Auxiliary Feedwater. System Workshop Dates: February 5 and 6, 1981, Atlanta, GA Course Duration: 16 h Vendor: INPO, Woodward Governor, Terry Corporation Limitorque

Description:

Provide information regarding auxiliary feedwater system operation, calibration, maintenance, and troubleshooting.

Emphasis on turbine driven pump systems.

Course

Title:

Nuclear Power-Educational Seminar Dates: April 20, 1981, to April 23, 1981, San Antonio, Texas

. Course Duration: 32 h Vendor: Southwest Research-Institute

Description:

Eleventh annual seminar.on inservice inspection techniques and quality

, assurance methods for nuclear power j plants.  !

Course

Title:

Operations Technology, VEGP Dates: February 5, 1983, to July 25, 1983 Amend. 16 _4/85

, i

c VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 54 OF 72) -

Course Duration: 17 weeks classroom, 8 weeks simulator Vendor: GPC

Description:

Reactor theory, health physics and chemistry, heat transfer and fluid flow, electrical theory, plant systems, integrated plant operation, Technical Specifications, normal and emergency operating procedures, emergency plan, and simulator training. This course led to SRO Certification.

Training, Other Course

Title:

Kepner-Tregoe Management Decisions Course Dates: July 31, 1978, to August 4, 1978, Miami, Florida Course Duration: 40 h Vendor: Florida Power & Light Co.

Description:

The Kepner-Tregoe method of problem solving, decision analysis, and potential problem analysis was taught (Genco II Course).

J. E. Swartzwelder, operations supervisor Date of Birth: April 6, 1951 Educational Background University of Pittsburgh B.S., mathematics Work Experience Georgia Power. Company ,

Position: Operations supervisor Dates: May 16, 1983 to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Plant Status: Under construction and startup-Job

Description:

Responsible for the safe and efficient operation of the plant during initial test program and commercial. operation.

Direct the preparation-of the security

.- ' procedures and plan. Assist training department in.the development and -,

implementation of operator training programs in order to ensure.a quality operations staff. ' Assist operations Amend. 16 '4/85 l u _ _

- _ - - s _-

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 55 OF 72) <

superintendent in the work planning and budget efforts. Act as operations superintendent in his absence.

Vice-chairman of the plant review board.

Position: Supervisor, VEGP Dates: October 1, 1981, to May 15, 1983 Location: VEGP, Burke Co., Georgia Plant Status: Under construction and startup Job

Description:

Supervise, co-ordinate, and assist in the training of GPC personnel. This training project consisted of course development (including visual aides),

classroom instruction, and simulator instruction. Performed the procurement and acceptance testing of the VEGP plant specific simulator. In conjunction with the manager-Vogtle project, utilizing past experience, ensured VEGP simulator mimicked actual plant response of a Westinghouse PWR. Managed the VEGP general physics office including scheduling and budgeting.

Position: Nuclear control operator Dates: September 1977 to September 1981 Location: BVPS Plant Status: At power-Job

Description:

Licensed by the NRC with the responsible operation of a nuclear power plant in a safe and efficient manner. Directed the activities of the plant auxiliary operators. Performed normal reactor operations, responsed to and mitigated .

the consequences of transient and emergency operations and the processing and disposal of radioactive waste.

Position: Auxiliary operator Dates: February 1975 to September 1977 Location: BVPS Plant Status: Startup and at power Job

Description:

Perform equipment checks, tests and surveillances. Record instrument

, readings for equipment performance trending. Assist the licensed operator in the performance of the duties.

Participated in necessary training programs to become a licensed operator.

Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 56 OF 72)

Position: Radiation control technician Dates: February 1, 1974, to February 1, 1975 Location: Shipping port Atomic Power Station Plant Status: Under modification

' Job Description Performed contamination and radiation surveys, calibrated survey instruments, processed waste shipments, monitored maintenance work to prevent over-exposure an the processing of personnel dosimetry.

Training, Nuclear Course

Title:

Reactor Operators License Training Dates: February 1, 1975 to September 1, 1977 Course Duration: 2400 h Vendor: NUS and Westinghouse

Description:

The content of this course contained the following:

1. Mathematics

2. Physics

3. Atomic Physics

4. Reactor Physics

5. Chemistry

6. Radiation Control Fundamentals

7. Materials

8. Electricity

9. Heat Transfer & Fluid Flow

10. Plant Systems

11. Integrated Plant Response

12. Accident & Transient Analysis

13. Mitigation of Core Damage

14. Simulator Training and the Use of Plant Procedures This training program consisted of all .

necessary training to successfully complete the NRC reactor operators license exam and ensure safe and efficient job performance.

-Course

Title:

Radiation Control Technician Training Dates: February 1, 1974 to July 1, 1974

-Course Duration: 1000 h Vendor .D. L. Company _ Personnel y

sDescription: This course contained the following

_ subjects:

1- 1. Basic _ atomic theory

2. Radiation control fundamentals

3. -Radiation control federal regulations Amend.316.-4/85.

I l

l VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 57 OF 72)

4. Radiation control procedures At the completion of this course of study.the final exam was an oral board before plant staff and Atomic Energy Commission Edward J. Kozinsky, operations supervisor Date of Birth: August 28, 1946 Educational Background Baylor University, 1968 B.S., chemistry Work Experience Georgia Power Company, nuclear Position: Operations supervisor Dates: January 23, 1984, to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Job

Description:

Under construction and startup responsible for safe and efficient

-operation of the plant during initial test program and commercial operation.

Direct review of control room design and normal, abnormal,'and_ emergency operating procedures.

Other nuclear Position: Senior / principal engineer -

Dates: February 28, 1978, to January 22, 1984 Location: GeneralPhysicsCorporatiogpChattanooga, Tennessee Job

Description:

Conducted research programs dealing with nuclear power plant control room design, operator performance reliability, and computer based operator aids. Worked with Electric Power Research Institute (EPRI) produced a performance measurement system for nuclear power

. plant simulators. Department'of Energy work. defined a disturbance-analysis and surveillance system (DASS) for nuclear power plant use.

. Amend. 16 4/85 L

I-VEGP-FSAR-13

. TABLE 13.1.2-1 (SHEET 58 OF 72) i

Nuclear Regulatory Commission. sponsored i research included the safety related ,

j operator action (SROA) program at Oak Ridge National ~ Laboratories and

, simulator studies on~ operator error

. rates at Sandia National Laboratories.

Position: Division Officer,..US Navy

~

Dates: February 1974 to February 1978

. Location: Atlantic SSBN645/SSN638

' Job

Description:

Responsible:for the. safe operation and

maintenance of naval nuclear power plant 4 systems. . Qualified as engineering I officer of watch.

Position: Instructor, US Navy

[- Dates: May 1969 - August 1973 Location: Naval Nuclear Power School Bainbridge,

Maryland I

~ Job

Description:

Develop lesson materials,and exams and

{ present a 12-week course of instruction.

1 on power plant. chemistry, radiological i fundamentals, and: reactor materials 1to p officer and enlisted students, p Nuclear. training

• i .

L Course-Title: US. Navy Nuclear. Power, Program..

Dates: .

August 1973-to! February 1974 Course Duration: 1280.h

Vendor

Nuclear Training Unit,-Windsor' Locks,-

I Connecticut

Description:

A program of' classroom and:on-the job,

. training?on the' SIC. pressurized water

reactor. . . .

Course Duration: ~ Qualified as engineering = officer of the

, watch. ,;

. Course

Title:

Engineer office school Datesi November 1975- ,

Course Duration: '160.h- -

I-

Vendor

US Navy,JCharleston, S.C.

-Description: -A~ program of classroom and self study to prepare forethe engineer officer.

,_ ' examination (on1the S5W naval' nuclear l- ,

power: plant)radministered by;the naval reactors. branch of the Energy Research'

.and Development ~ Agency-(ERDA).

'~ ~

t. .

=CourseETitle: ' Hot.LicenseLTraining

[ Dates: . March to. April 1978- ~

l.  : Amend.416 4/85-l

.]

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 59 OF 72)

Course Duration: 240 h Vendor: General Physics Corporation

-Description: A program of classroom (120 h) and simulator (120 h) training for hot license certification on the Sequoyah (Westinghouse-PWR) plant.

Other training University of Tennessee, Chattanooga

1. Fluid flow

2. Analysis methods (advanced differential equations)

3. Statistics William Lee Burmeister, operations supervisor Date of Birth: May 4, 1955 Educational Background University of Wisconsin, 1977 B.S., nuclear engineering Work Experience Georgia Power Company Position: Operations supervisor Dates: November 10, 1984, to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Job

Description:

Under construction and startup direct preparation of procedures and schedules for the startup test phase of the ,

initial test program.

Position: Shift supervisor. .

Dates: January 9,.1984, to November 9, 1984 Location: VEGP Plant Status: Under construction and startup Job

Description:

Direct preparation of procedures and schedules for the startup test phase of

-the initial test program. Obtained SRO instructor certification. Acted as duty shift supervisor.

Other nuclear Position: Lead shift engineer / lead shift. technical advisor Amend. 16 4/85 i-

i VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 60 OF 72)

Dates: October 1981 to January 1984 Location: Palisades Plant, Covert, Michigan Plant Status: Operating Job

Description:

Supervised five shift engineers / shift technical advisors; maintained all administrative and working level department procedures; coordinated 4C departmental audits; provided relief-support for shift supervisors.

Developed and implemented technical specifications limiting conditions for-operation pilot program manual to improve operator compliance with technical specifications; coordinated complete revision to all operations department administrative procedures; researched and provided recommendations for improved reactor coolant pump seal performance; performed trend analysis of reactor. trip events; coordinated rewrite of emergency /off normal operating procedures in accordance with NUREG-0737.

Position: Shift technical advisor Dates: November 1979 to October 1981 Location: Palisades Plant, Covert, Michigan Plant Status: Operating Job

Description:

Shift technical advisor as required by Short-Term Lessons Learned NUREG-0578.

Principal responsibilities included troubleshooting equipment / system operational problems; acting as an

-accident assessment consultant to the shift supervisor; providing' plant operating experience assessments to management. Acted-as utility representative for combustion engineering workshops to develop generic emergency operating procedure guidelines for combustion engineering plants.

Participated in complete rewrite-and

' technical review of plant technical specification surveillance program which subsequently received INPO good practice standing.

Position: Quality assurance engineering Dates: August 1977'to November 1979

, Location: Palisades Plant, Covert, Michigan l Plant Status: Operating Amend. 16 4/85 k.

VEGP-FSAR-13 TABLE.13.1.2-1 (SHEET 61 OF 72)

Job

Description:

Certified lead auditor per ANSI N45.2.23. Participated in approximately ton internal and external audits including Bechtel Power Corporation for seismic engineering analysis, EXXON Nuclear Company for Palisades Reload Fuel, and Combustion Engineering Company for control rod drive seal redesign project. Provide on-the-job training for starting quality assurance engineers. Conducted surveillances of maintenance, operations and radiation protection activities.

Nuclear training Course-Title: Piping Design and Fabrication Dates: March 12, 1979, to February 15, 1979 Location: Minneapolis, Minnesota Course Duration: 28 h Vendor: Technical Seminars, Inc.

Description:

ASME Section III, ANSI B31.1, piping supports, pressure design, piping system analysis and NDE.

Course

Title:

CRDM Refurbishment Dates: January 1, 1978 to January 3,1978 g(

Location: Muskegon, Michigan Course Duration: 24 h Vendor: Consumers-Power Company

Description:

Training for complete disassembly, repair, and reassembly of Palisades control rod drive mechanisms.

Course

Title:

Nuclear QA Engineering .

Dates: October 24, 1977, to October 29, 1977 Location: Edison, New Jersey Course Duration: 35 h Vendor: Statamatrix

Description:

Auditing, ANSI Standards, statistical techniques, reliability and NDE. .

Other' training Course

Title:

Control Room Management

_ Dates: November 19, 1984, to November 21,.1984 Location: VEGP-Course Duration: 24 h .

Vendor: General Electr'ic Amend. 16 14/85 L.

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 62 OF 72)

Description:

Situational analysis, problem analysis, s decision analysis, potential problem s

analysis Course

Title:

Problem Solving Decision Making Dates: February 17, 1983, to February 19, 1983 Location: South Haven, Michigan Course Duration: 28 h Vendor: Action Management Associates, Inc.

Description:

Several aspects of management including group effectiveness, deviation analysis, creative problem solving, decision making, planning and anticipating problems, situational analysis, and application planning.

Course

Title:

SRO Management Training Dates: December 13, 1982, to December 17, 1982 Location: South Haven, Michigan Course Duration: 35 h Vendor: MDI Systems, Inc.

Description:

Videotape-based role playing to demonstrate general principles of management under situations of motivating safe performance, handling a performance problem, negotiating cooperation between departments, creativa problem solving and decision making.

Course

Title:

Supervisory / Management Skills-Workshop Dates: November 2, 1981, to November 6, 1981 Location: Palisades P1m*f; Course Duration: 32 h Vendor: NUS Train? rj arporation

Description:

Lectur: . r.1 le playing several aspects of mani, ,eme..: Jncluding interpersonal communications,. leadership,flabor relations, occupational safety, stress management, crisis management, motivation and human' behavior.

Samuel A. Bradley, operations supervisor Date of Birth: July 4, 1946-Educational Background-University of New Mexico, 1968 B.S., electronics engineering Amend. 16 4/85

- ~ . . ,

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 63 OF 72)

Work Experience Georgia Power Company Position: Operations supervisor Dates: August 23, 1982, to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Plant Status: Under construction and startup Job

Description:

Coordinate company employees, contractors, and vendors in the definition, purchase, and storage of initial spare parts allowance.

Currently responsible for development of operating procedures Position: Lieutenant Commander, U.S. Navy / Department of Energy Dates: 1978 to 1979 Plant Status: Operational Location: Naval Reactors Facility, Idaho,, National 3g Engineering Laboratory.

Plant Status: Operational Job

Description:

Training assistant to the Department of Energy manager of-operations.

Responsible for training provided to Navy and Westinghouse personnel at three operating pressurized water reactor plants. Conducted audits of a program which annually trains 1600 students at a cost of 7.2 million dollars. Made improvements in training and operations procedures. Conducted special audits of

, radiological controls and maintenance.

Position: Lieutenant Commander, U.S. Navy a Dates: 1975 to 1978 Location: U.S.S. Hammerhead (SSN 663), Norfolk, Virginia Plant' Status: Operational and refueling overhaul Job

Description:

Engineer officer. . Responsible for supervision, operation, and maintenance of nuclear propulsion and auxiliary systems.

Amend. 16- 4/85 Y f

l l

l

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VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 64 OF 72)

Position: Lieutenant, US Navy Dates: 1973 to 1974 Location: S1W Prototype, Naval Reactors Facility, Idaho National Engineering Laboratory.

Plant Status: Operational Job

Description:

Production training assistant and leading engineering officer of the watch. Managed and taught nuclear power plant operations and maintenance.

Position: Lieutenant, US Navy Dates: 1970 to 1972

-Location: U.S.S. Puffer (SSN 652), Pearl Harbor, Hawaii Plant Status: Operational Job

Description:

Watch officer, department head, and division officer.

Nonnuclear Experience Position: Electrical Supervisor, FMC Phosphorus Chemical Divisicn Dates: 1981 to 1982 Location: FMC Plant, Pocatello, Idaho Plant Status: Operational Job

Description:

Responsible for maintenance of power distribution and process control equipment at the largest elemental phosphorus. plant in the United States.

Supervised two foremen and a thirty-three-man union ship. Improved the electrical safety program.

Initiated improvements in switchgear room air conditioning, instrument calibration, and startup procedures.

Position: Project engineer, EG&G Idaho, Inc.

Dates: 1979 to 1981 Location: Radioactive Waste Management Division, Idaho National Engineering Laboratory N/A Plant Status: N/A Job

Description:

. Managed the Shallow Land Burial Stabilization Project. Responsible for startup and direction of a 265 thousand dollar effort to write the closure and

__ stabilization plan for the Subsurface

' Disposal Area-(SDA). Conducted audits for facility manager.~ Coordinated disposal of highly radioactive internals' from a pressurized water reactor.

' Amend. 16 4/85 t-- _

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 65 OF 72)

Position: Junior engineer University of California Dates: 1968-to 1969

. Location: Los Alamos National Laboratory, Los Alamos, New Mexico Plant Status: N/A job

Description:

Designed and tested instruments for underground nuclear weapons tests.

Nuclear Training Course

Title:

SRO Certification

. Dates: November 1983 to January 1984 Course Duration: 2 months classroom, 1 month simulator Vendor: GPC

-Description: Reactor theory, health physics, chemistry, heat transfer, fluid flow, electrical theory, plant systems, integrated plant operation, technical specifications, operations procedures, emergency plan, simulator Course

Title:

Operations Technology Dates: April to September 1983 Course Duration: 4 months classroom, 1 month simulator Vendor: GPC

Description:

(Same as above)

Course

Title:

Engineer officer Dates: January to March 1974 Duration: 4 months Vendor: US Navy

Description:

Similar to above plus maintenance Course

Title:

Nuclear Prototype Training

-Dates: January to June 1970 Course-Duration: 6 months Vendor: Department of. Energy

Description:

(Similar to above)-

Course'

Title:

Nuclear Power School Dates: - July to DecemberL1969 Course Duration: 6 months Vendor: .US Navy

Description:

= Nuclear power theory Nonnuclear Training-Course

Title:

Advanced Submarine School Dates: . January-to June 1975 Course Duration: 6, months Amend. 16 4/85

I VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 66 OF 72)

Vendor: US Navy

Description:

Supervisory skills, submarine operation, and warfare Course

Title:

Mark 48 Torpedo Dates: May 1972 Course Duration: 1 week Vendor: US Navy

Description:

Construction, handling, and use of Mark 48 torpedo Course

Title:

Nuclear Weapons Dates: August 1971 Course Duration: 2 weeks Vendor: US Navy

Description:

Construction, handling, and use of nuclear weapons Course

Title:

Basic Submarine School Dates: July 1970 Course. Duration: 1 month Vendor: US Navy

Description:

Basic submarine systems and operation Mark J. Ajluni, operations supervisor Date of Birth: December 13, 1955 Educational Background University of Florida, 1979 B.S., nuclear engineering Work Experience Georgia Power Company Nuclear ~GPC Position: Operations supervisor Dates: November 10, 1984 to present Location: Vogtle Electric' Generating Plant, Waynesboro, Georgia Plant Status: Under construction and startup Job

Description:

Primary duties include I.T.P.

energizction supervi'sor, supervising the onshift operations staff as the operations supervisor, service as a test review board member, and directing Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 67 OF 72) operations coverage of the work planning group.

Position: Shift supervisor Dates: December 5, 1983, to November 10, 1984 Location: VEGP Plant Status: Under construction and startup Job

Description:

Primary duties included I.T.P.

energizationffor initial plant energization,vsunervisor responsibre) supervising the onshift operation staff as a shift supervisor, and obtaining a VEGP NRC, SRO certification.

Position: Shift supervisor Dates: October 17, 1983, to December 5, 1983 Location: Plant Hatch Plant Status: Commercial operation Job

Description:

As a shift supervisor work was performed as control room supervisor on shift and as a maintenance shift supervisor.

Primary responsibilities were to coordinate plant maintenance activities with unit operation.

Position: Simulator engineer Dates: January 9, 1982, to October 17, 1983 Location: Plant Hatch Plant Status: Commercial operation Job

Description:

Primary job responsibilities were to update the Hatch simulator to perform as realistically as possible to the real plant to work the simulator maintenance foreman in design modifications and computer programming. Attended the acceptance test program of the Hatch simulator at the Link-Singer factor in Silver Springs, Maryland, from March through June 1982. Other job responsibilities include operator license requalification training, administering license requalification exams, simulator certification exams, teaching nonlicensed plant operators and.

GPC management officials in reactor theory and. plant. systems, developing licensed operator / simulator training aids, and to assist in the Hatch emergency preparedness drill which is performed on the Hatch simulator.

Amend. 16 4/85

VEGP-ESAR-13 TABLE 13.1.2-1-(SHEET 68 OF 72)

Position: Senior methods and training specialist Dates: May 1, 1981, to January 9, 1982 Location: Plant Hatch Plant Status: Commercial operation Job

Description:

Primary job responsibilities were to train nonlicensed plant operators in the areas of reactor theory, physical sciences, and to develop training materials to be used for the purpose of NRC licensing plant operators. As a training instructor, supervised classes sized between 12 to 18 students.

Supervision responsibilities included maintaining classroom discipline and order, timekeeping, and_ counseling.

During this time frame and earlier as a methods and training specialist along with teaching responsibilities, attended licensed operator training classes on plant _ systems, BWR technology, and spent approximately 3 months on shift in the Hatch units main control room as an operator in training.

Position: Method and training specialist Dates: November 10, 1979, to May 5, 1981 Location: Plant Hatch Plant Status: CommercialJoperation Job

Description:

Primary job responsibilities were the same as described above'for Senior methods and training specialist.

Position: Junior Engineer Dates: September'10, 1979, to November 10,-1979 Location: Plant Hatch Plant Status: Commercial operation o-

~ Job

Description:

As a Junior Engineer, worked in the plant engineering department, reporting to the " balance of-plant" engineering supervisor. Primary job responsibilities were performing design change requests for plant systems and completing "as built" notices on plant modification.

Nuclear Training Course

Title:

GPC-licensed operator training program for Plant Hatch'(GE-BWR 4).

Amend. 16 4/85 a __ __

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 69 OF 72)

This program consists of nuclear theory, BWR technology, BOP technology, simulator, and main control room duties.

GPC SRO instruction certification training program for Plant Vogtle (WH-PWR 4 Loop). This program consists of 6 months of nuclear theory, PWR technology, BOP technology, and simulator training.

David-W. Schreiber, operations supervisor

~

Date of Birth: July 31, 1947 4

Educational Background Richland Community College, 1978 Associate in Science Work Experience Georgia Power Company-nuclear Position: Operations supervisor Dates: March 19, 1984, to present Location: Vogtle Electric Generating' Plant, Waynesboro, Georgia Plant Status: Under construction

, Job

Description:

Responsible for development or radwaste procedures, program and manning. Work with and provide operations concerns to work planning group. Participate in plant testing, startup, and commercial operation of the plant as an operations supervisor.

10ther Nuclear Position: Shift supervisor, Public Service of.

Indiana Dates: April 1977 to January 3, 1984 Location: Marble Hill Nuclear Plant .

Jefferson.Co., Indiana Plant-Status: Under construction and startup testing Development of. operation and~

Job

Description:

administration procedures, served on evaluation teams for safety assessment system and control room review,-

Amend. 16 4/85 L1

VEGP-FSAR-13 TABLE'13.1.2-1 (SHEET 70 OF 72) supervised startup and operation of switchyard and various plant systems prior to construction shutdown.

Position: Assistant shift supervisor, Illinois Power Company Dates: April 1977 to April 1979 Location: Clinton Nuclear Station Clinton County, Illinois Plant Status: Under construction Job

Description:

Development of operation procedures and system review for operation concerns.

Position: Reactor operator Indiana and Michigan Power Company Dates: September 1973 to April 1977 Location: DC Cook Nuclear Plant Plant Status: Preoperational testing, startup testing, commercial operation, and first refueling.

Job

Description:

Responsible for the safe and efficient operation of the reactor and plant while adhering to requirements as found in the ESAR and procedures.

Nuclear training 1

Course

Title:

BWR Familiarization-Dates: September 1978 to November 1978 .

Course Duration: 10 weeks

' Vendor:

Description:

GeneralPhysicsatIllinoisPower[BWR Plant system familiarization a4&en reactor theory, core thermal limit design; heat transfer,and fluid flow. gf. .

Course

Title:

License Training Program Dates: September 1973.to March 1975 Course Duration: 17 weeks Vendor: .

Indiana and Michigan Power Company

Description:

Reactor theory, health physics and chemistry, heat transfer and fluid _ flow, plant systems, integrated plant operation, technical specifications, normal and emergency procedures and emergency plans.

Course

Title:

Nuclear Plant Operation (Prototype)

Dates: November 1968 to May 1969 Course Duration: .6 months at prototype Amend. 16 4/85

VEGP-FSAR TABLE 13.1.2-1-(SHEET 71.0F 72)

Vendor: US Navy

Description:

. Check out and qualification on land based naval nuclear plant.

~ Course

Title:

Basic Nuclear Power School Dates: May 1968 to October 1968 Course Duration: 6 months classroom Vendor: US Navy

Description:

Math, physics, thermodynamics as applied to power plants, reactor theory, plant technology.

Other training Course

Title:

Public-Service Indiana, shift technical advisor, program Dates: December 1980 to June 1983 Vendor: Purdue University Course Duration: 28 h

Description:

Pl. Anal'Geo Calc I, Calc II Multivariate Calc, Lin Alg Diff Equats, thermodynamics, basic mechanics 1, and physics.

Charles F. Meyer, operations supervisor Date of Birth: March.21, 1944 Educational Background Iona College,'New Rochelle, New Rochelle,-New York, 1978' B.S., industrial management / supervisor Work Experience Georgia Power Company, nuclear Position: Operations' supervisor Dates: April 30, 1984, to present Location: Vogtle Electric Generating Plant, Waynesboro, Georgia Plant Status: .Under construction and startup

. Job

Description:

Responsible for onshift operations, flushing,.startup test, and hot functional' test programs. Direct the

. operations support of the. initial test program in the prerequisite and preoperational test phases. . Member of

.the test review board. 'Act in behalf of Amend. 16 4/85

w. . _1

f VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 72 OF 72) the operations superintendent in his absence.

Other nuclear Position:

Dates: January 1984 to April 1984 Location: Modification Systems, Inc. (MSI)

Plant Status: Commercial operation Job

Description:

Responsible for the performance test program of Consolidated Edison's Indian Point Singer Link simulator. Assisted-MSI program engineers in trouble.

shooting and problem solving the operational aspects of simulator response.

Position: Shift supervisor Dates: April 1983 to January 1984 _

Location: Public Service Company of Indiana Marble Hill Nuclear Station Plant Status: Under construction and startup Job

Description:

Responsible for the onshift operation of turned over equipment, liaison _with

+

construction /startup groups, and support of prerequisite and preoperational testing of constructed systems.

Supervised nine' people in a shift work capacity. Responsibility within the operations department, for the abnormal

- , procedures, annunciator response procedures, TMI~ action items, and varied operating procedures.

Position: Training supervisor Dates: July 1979 to April 1983 Location: Marble Hill construction and startup Plant Status: Under construction and startup Job

Description:

Responsible for the activities of the station training section. This includes the design, implementation, and coordination of training programs to

+

comply with the applicable Code 10 of

.i Federal Regulations, ANSI /ANS guidelines, and INPO guidelines. Also,

, during this-period,- responsible for evaluation and justification or manning levels-(present staffing 12);

preparation and control of training

' budget; preparation of the training section of the Marble Hill FSAR; and Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 73 OF 72) cost effectiveness of vendor materials, or in-house preparation of discipline programs, lesson plans, and training procedures.

Position: . Senior site engineer, Sargent & Lundy l Engineers Dates: June 1978 to July 1979 Location: Cincinnati Gas and Electric Company Wm H. Zimmer. Nuclear Power Station Plant Status: Under construction and preoperational testing Job

Description:

Responsibilities included assisting the client with the establishment of-preoperational testing concepts and methods to be used for the test program; preparation and review of preoperational test procedures and the implementation

, of those procedures for HVAC systems; preparation of instrument and mechanical checkout and calibration procedures for' HVAC; evaluation of test results for submittal to.the station review board; and evaluate system / component problems and provide engineering resolutions for evaluation by the design engineers.

Certified to N45.2.6 Level II.

Position: Site engineer Dates: February 1978 to June 1978 Location: Sargent and Lundy Engineers, Chicago, Illinois Plant Status: Construction and testing Job

Description:

Promulgation of written procedures to validate the design of plant ~ systems as defined in the applicable state and federal standards and codes.

Responsibilities included preparation, performance, and evaluation of test activities during the post-construction and startup phases of nuclear power-plant work and other~special assignments; i.e., Inservice Inspection Program as<per Section XI of ASME Codes,

_ that pertains to the plant startup program.

Position: Senior reactor operator Dates: June 1972 to February 1978 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.1.2-1 (SHEET 74 OF 72)

Location: Indian Point Station Units 2 and 3 Consolidated Edison of New York Plant Status: Start of phase, commercial operation Job

Description:

Responsibilities included liaison with the prime contractor, WEDCO Corporation, for testing during the construction phases, and concurrent with the startup program. Supervised flush hydrostatic, and system preoperational tests.

Control room operator for primary system cold hydro, plant hot functional initial criticality, and power physics testing through commercial operation.

, Position: Engineering watch supervisor / diver Dates: November 1963 to May 1971 Location: US Navy Submarine Service Plant Status: Operational Job' Description Watchstanding and maintenance on a Naval S5W PWR.

Nonnuclear experience Position: HVAC technician Dates: June 1971 to June 1972 Location: Connecticut Mutual Life Insurance Plant Status: Operational Job

Description:

Building maintenance division, specializing in maintenance and. repair of various closed environmental systems, and support systems. These included Johnson Controls, steam heating, refrigeration, air conditioning, chilled 4

water cooling, fans and their drive components,' air compressors, D-type boilers, and diesel engines.

1 Nuclear training Course

Title:

Plant Vogtle Switchyard Dates: September 10, 1984, to September 14, 1984 Course Duration: 40 h Vendor: .

Georgia Power /HDR

Description:

Classroom and field training on 230-kV switchyard components.

Course

Title:

Operator License Class Dates: June 1972 to Course Duration:

Vendor: Consolidated Edison of New York Amend. 16. 4/85

i. .

VEGP-FSAR TABLE 13.1.2-1 (SHEET M

Description:

Classroom, In-plant.OJT, simulator training for NRC licensing exam.

Amend. 16 4/85 .

VEGP-FSAR-13 TABLE 13.1.2-2 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 5 or 6 DEFUELED OS 1 1 1 SRO 1 1 1 RO 3 3= 2 NLO 3 3 2 STA'** 1 1 1 M' UNIT 1 IN MODE 5 OR 6 UNIT 2-IN MODE:

POSITION 1, 2, 3, or 4 5 or 6 DEFUELED OS 1 1 1 SRO 1 O O

~RO 3 2 1 NLO -3 3 1 STA'1' 1 O O .x UNIT 1 DEFUELED UNIT 2 IN MODE:

POSITION 1, 2, 3, or 4 5 or 6 DEFUELED OS 1 1 0 SRO 1 O O RO 2 1 O NLO. 2 1 0 STA'@ 1 'O O k

a._ The STA.is not required on shift if.the qualifications of the. operations supervisor are upgraded.to fulfill the. >

requirements _of the STA position.

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AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AA AAAAAAAAA AAAAAA A AAAAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAAAAA AAAAAAAAA AAAAAAAAAAAA DOCUMENT ID: 0365V DOCUMENT NAME: FSAR 13.1.3 VOGTLE OPERATOR: Doris Hill AUTHOR: Jim Valekis DATE: 03/14/85 NOTES: Amend. 15 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A AA A A A A A A A A A A A A A A; A A A A A A A A AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA PLEASE RETURN THIS TITLE PAGE WITH ALL FUTURE REVISIONS l

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VEGP-FSAR-13 13.1.3 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.

Enperience - 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 nuclear power plant startup, operation, maintenance, or technical services under the direction of appropriately experienced personnel'.

13.1.3-1

I I

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 militar , nonstationary, or propulsion nuclear plants may qualify as equivalent experience on a one-for-one time basis.

4 -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 y 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 equivalent to nuclear power 4

plant experience on a one-for-one time basis.

f 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.

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. H A o A R c T T e S R r R D art b .

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- E od a e l v t r u r s o 3 I V/ r t pr n ep' n o r i s n R e s e n e i s o v i r a n 1 E l n p fs r u f s r v o m a o ir i

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i rir e d p r o v p e i r e 1 T ete t p tn u na u s t e s r u p v o r E D P gag i ara n s e s c n e

p i e s r u r f o L N -C nen u e s i

us r v p o s e f B A E apa s nn dg c y d u e s p e u c y n e s c i y A V mom - n ei n h e n p n v r s n r T N O l rl o tr r i ne a

n p tg nn o u l a r o a n e p at a o i s C n t I

aaa e g a rn t i e e h ii t i e e ar T

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el e a r ei n lt ei r f e n s o n n o ncn n e pg i an pa e i t i b a i b U

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nC e isp a r n a 1

n eR c m t N t n l dN n mn s se n a n o a n a eo g r rs e S

I s

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i

. TABLE 13.1.3-1 (SHEET 2 OF 2) (FIRST HALF)

' Recommended Experience f vears)

License Total Nuclear . Senior Powe r Power Other- Academic Reac to r Reactor.

ANSI N18.1 Title VEGP Title Plant Plant Apolicable T ra i n i no Ope ra to r Ope ra to r

- Instrumentation and I and C foreman 5 cont rol I

Professiona l - technical Plant engineer ( reactor 2 4 eng i nee r) l Shif t technica l advisor 4 Operators to be NRC Plant operator 2 1 X licensed Assistant plant operator 2 1 X Technicians I and C technicians 2 Laboratory technician 2 l

l Repairmen. Mechanic' 3 Electrician 3 Technical support personnel l

Eng inee r-in-cha rge Plant engineering 3 4 supe rvisor Other personnel Other personnel

a. Senior reactor operator license is not required for plant manager, but he or the assistant will have the background required to l sit for examination.

Required by NUREG-0737.

, b.

t I

c. Shif t technical advisor training certified by CPC. See pa rag raph 13.2.2.1.5 for shift technical advisor tra ining.

l' l

b f i ' s * , ,  ;' ' t ;' ='t' t ,

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- n p i fs r- u f v r r s r v s e m 3 E t o o re o e s o i e r 1 i rir d p ep so v p e i r e D -T ete t p tn u s t r u p v o r u na s c n u n e s ro. su r f o ee E N gag i i L A P ara n s e dg i e s v a p f B C nen u e c y s d n s r m ep er u s ce i y s p u c y A N E apa s nn s n r T O -V mom - n ei n h e n n v r I o tr a p- tg o us fo l a r o a o T l rl r i ne n nn i a n e p at C n t A aaa e g a trn ie e h ii t . i r t' u r e e ar C rer t t- rn a t t d n n o t

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ml m a i c hi I

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

I l

, TABLE 13.1.3-1 (SHEET 2 OF 2) (SECOND HALF) l t

j- Succested Education (Yea rs)

Amount of Related'- Education

• Technical Creditable for ANSI N18.1 Title VECP Title Academic T ra i n ino Expe ri ence Remarks 2 6 months experience in I Instrumentation and . I and .C foreman 2 or is cont rol nuclea r I and C.

Professional - technical Plant, engineer ( reactor engineer)

Shift technical advisor (c) .

i .

Operators to be NRC Plant operator High school diploma or licensed equivalent requ i red. ,

Assistant plant operator High school diploma or equivalent required.

Technicians I and C technicians 2 Laboratory technicians 1 Repairoen Mechan ic

Electrician  ;

i Technical support personnel Eng inee r-In-cha rge PIant engineering ,

supe rvi so r l

.3 j Other personnel . Other personnel Shati be com- High school diploma- '

petent in or equivalent re-( their. field quired for quality control personnel.

1 I

t l

Amend. 15 3/85

% - , - - -- = su m e w e 6

DOCUMENT

SUMMARY

l AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAAAAAA A AAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAA AAAAAAAAAA AAAAAAAAAA AAAAA AAAAA AA AAAA AA AAAA AAAAAAAAA AAAAAAAAAAAAAAAAAAAAAAAA AAAAAA AAAAAAAAAAAAAAAAAAAAAAAA AAAAAAAAAAA DOCUMENT ID: 0366V DOCUMENT NAME: FSAR 13.2.1 VOGTLE OPERATOR: Doris Hill AUTHOR: Jim Vakekis DATE: 03/14/85 NOTES: Amend. 16 AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA PLEASE RETURN THIS TITLE PAGE WITH ALL FUTURE REVISIONS 9

VEGP-FSAR-13 13.2 TRAINING 13.2.1 LICENSED OPERATOR TRAINING The VEGP.: licensed staff will consist of individuals with

'significant differences in previous education, training, and experience. The licensed training programs have been formulated to provide the required training based upon the individual's prior experience. These programs are designed to provide the highest degree of operator proficiency by effectively using the VEGP simulator.

13.2.1.1 Training Programs The details of typical training programs, including syllabus, duration, classroom, and on-the-job training, are contained in

-tables 13.2.1-1 through 13.2.1-5. The programs described in these tables will remain the same for both units before and after initial fuel loading.

These programs are designed to train personnel with various 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 supervising-the instruction. The VEGP training department is-shown in figure 13.2.1-1. The qualifications of instructors and a description of the instructor requalification program are found in paragraph 13.2.1.3.3.

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

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

Waivers will be granted only if one of the conditions listed below has been satisfied, e A previous course of instruction has been comploted which contained the same topics and wast at least the duration of the-course.being waived. The course may have been completed at VEGP or another facility. For example,:a trainee who' completes a course of instruction at, Plant Hatch meeting the above criteria would.not.be required to repeat the course at VEGP.

e .A previous course of instruction has been completed which contained all of the objectives of the course being waived. This would lua determined by. comparison of 13.2.1-1 Amend. 16 4/85

i'

\

VEGP- FSAR-13 the objectives of the course completed and the course being waived. If the already completed course of instruction did not meet all required objectives, these additional topics may be taught and course completion may be granted.

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

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

13.2.1.1.1 Nuclear Power Plant Theory Training shall be provided in relevant aspects of nuclear power plant theory as required by 10 CFR 55 and NUREG 0737, paragraph k Theamountoftrainingrequiredis) l I.A.2.1, enclosure 2.

estimated in tables 13.2.1-1 through 13.2.1-5.

13.2.1.1.2 VEGP Systems ..

Training shall be provided in VEGP systems and procedures as required by 10 CFR 55, as indicated in tables 13.2.1-1 through 13.2.1-5.

13.2.1.1.3 VEGP License and Technical Specifications Training shall' be provided in' VEGP license and technical specifications as requiredToy 10 CFR 55, as indicated in tables

13.2.1-1 through 13.2.1-4.

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

13.2.1.1.5 Control Room Operations L Training shall be provided in control room operations as l required by,10-CFR 55, as indicated in tables.13.2.1-1 through 13.2.1-5. The training shall be accomplished-by utilizing a combination of classroom-instruction and hands-on operating l practice on the.VEGP plant-referenced simulator. The training will prepare the candidate for the NRC simulator portion:of the p operating examination.

13.2.1-2 Amend. 16 4/85

VEGP-FSAR-13 13.2.1.1.6 Mitigating Core Damage Training for mitigating core damage will have the course content as described in NUREG-0737, item II.B.4, and will be taught during the courses scheduled in the syllabus, as shown in tables 13.2.1-1 through 13.2.1-5.

13.2.1.1.7 Hot Participation / Observation and Walkthrough Training The following paragraphs define the meaning of the terms hot participation experience, observation training, and walkthrough training. Approximate duration for these types of training are specified in tables 13.2.1-1 through 13.2.1-5. The training will prepare the license applicants for the plant walkthrough portion of Nuclear Regulatory License examination.

Hot participation experience is direct involvement in review and discussions leading to decisions relative to operation of a commercial nuclear power plant, or direct hands-on operation as a trainee at a commercial nuclear power plant. Hot participation experience requirements apply only prior to VEGP achieving 20 percent power.

Observation training constitutes assignment to an operating shift for the purpose of training. Emphasis is placed on observing as many shift activities as possible, e.g., shift relief, operator rounds, local equipment operations, control room activities. Hands on participation may be conducted under the observation of a qualified operator. Observation training requirements apply only after VEGP reaches 20 percent power.

Walkthrough training is a systematic program to become familiar with plant equipment and layout. It may be conducted concurrently with observation training or may be conducted as a separate program.

13.2.1.1.8 Review and Audit A short period of time will be allocated for each individual license candidate to review material and prepare for a comprehensive. audit. examination. The effectiveness of the training program in the case of each trainee will be evaluated from the results of a series of written, oral, and manipulation examinations. Applicants for_ Nuclear Regulatory Commission INRC). 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, Amend. 3 1/84 13.2.1-3 Amend. 16 4/85' L

s VEGP-FSAR-13 Georgia Power Company (GPC) will certify to the extensive operating experience based upon the individual's If the satisfactory individual fails to progress in the training program. demonstrate the ability to pass GPCan will audit examinat ability to properly manipulate VEGP simulator controls, request that the NRC not administer an examination to this individual.

Occasionally, the audit examination may uncover a weak area in an individual's knowledge, but if GPC believes that the individual has sufficient time to correct the problem, certification will not be withdrawn.

13.2.1.1.9 Operator Training Schedule The bar chart in figure 13.2.1-2 shows the schedule of the licensed operator training program in relation to the schedule for preoperational tests, fuel load, criticality, and the If fuel loading is expected time for license examinations.

significantly delayed, the VEGP license requalification program will be used to maintain operator proficiency.

Several specific training items for licensed operators identified in tables 13.2.1-1 through 13.2.1-5 (and included in general topic format in figure 13.2.1-2) will beThe taught just items not prior to the precritical license examinations.

yet included as a part of training, but to be taught prior to licensing include:

e VEGP Operating Procedures e VEGP Fuel Handling and Core Alteration e Mitigating Core Damage e VEGP walkthrough Training e Reactor Startup (if required by Section 13.2.1.2) e Plant Walkthrough Audit Exam Personnel listed on figure 13.2.1-2 without an asterisk have completed training in the time frames indicated with the exception of items listed above.

13.2.1.2 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-Amend. 10 9/84 13.2.1-4 Amend. 16 4/85

r ,

VEGP-FSAR-13 water reactors. The cold license training program will also contain a program of 10 reactor startups on a research/ test type reactor to gain actual "at the controls" experience. Personnel with prior Navy nuclear experience as an engineering watch officer, engineering watch supervisor, reactor operator, or other equivalent positions or those who have prior commercial nuclear plant licensed operator experience or those who have prior test reactor experience shall be exempted from 10 reactor startup requirements. A combination of the preceding will satisfy the experience requirements of NUREG-0737, items I.A.2.1. The details of the simulator program are contained in tables 13.2.1-1 through 13.2.1-5.

The VEGP simulator will conform with the guidance given in Regulatory Guide 1.149. Since digital software does not drift or change, retesting of previously verified response would be redundant or unnecessary. Performance testing will be conducted for any hardware or software modifications made to the simulator as a result of plant changes that affect training. The simulator will be tested continuously while it is in use.

Operators and instructors will identify any incorrect simulator responses or inconsistencies. These discrepancies _shall be documented at the time of discovery, investigated by the simulator maintenance crew, and corrected as appropriate. The continuous feedback system utilizing experienced operators and instructors will adequately exercise and. test the simulator.

More immediate follow through on identified discrepancies will-be possible in comparison to conducting annual performance testing. This continuous, ongoing simulator improvement program exceeds the requirements and will be conducted in lieu of annual performance testing. Documentation of discrepancy identification, investigation, and resolution will be retained as a part of the simulator performance documentation.

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.

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 (3.2.1-5.

Amend. 10 9/84~

13.2.1-5 -Amend. 16. 4/85

VEGP-FSAR-13 13.2.1.3.2 Licensed Operator Requalification Program

-The licensed operator requalification training program will be implemented within 3 months after issuance of an operating license.

The. program shall be continuous and may be conducted as an

-intensive program of several weeks duration each year or may be spaced.out over a period of up to 24 months, with elements of the program occurring on a periodic basis.

Records of the requalification program shall be maintained.for a period of 2 years from the date of the recorded event to document the participation of each licensed operator or senior operator in the requalification program. The records shall contain copies of written examinations administered, the answers given by the licensee, results of evaluations, and documentation of any additional training administered in areas in which an operator or senior operator has exhibited deficiencies. An original or reproduced copy or microfilm copy will fulfill these record retention. requirements. The reproduced copy or microfilm copy will be authenticated by authorized personnel and will be capable of producing a clear and legible copy after storage for a period of 2 years.

13.2.1.3.2.1 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. PlantJprotection systems.

E. Engineered. safety systems.

F. Procedures.

G.- Radiation control and~ safety.

H. Technical specifications.

I. Applicable portions of 10 CFR.

4

. Amend. 10 l9/84 t

_ 13.2.1-6 Amend. 16 4/85

VEGP-FSAR-13 J. Quality assurance for operations.

K.- Major upcoming events.

L. Heat transfer, fluid flow, and thermodynamics.

1. Fluids and matter.

2. Fluid statics.

3. Fluid dynamics.

4. Heat transfer by conduction, convection, and radiation.

5. Change of phase _- boiling.

i 6. Burnout and flow instability.

7. Reactor heat transfer. limits.

M. Mitigation of accidents involving a degraded core.

1. Incore instrumentation.

2. Excore instrumentation.

3. Vital instrumentation.

4. Primary chemistry.

5. Radiation monitoring.-

6. Gas generation.

13.2.1.3.2.2 On-the-Job Training. .

A. Reactivity Controls

~

Each licensed operator will, during the term of his

license, perform a minimum of 10 reactivity control manipulations in a_ combination of reactor startups,-

reactor shutdowns,'or other control manipulations

-which demonstrate his skill and/or familiarity with reactivity control systems. Each~ senior. reactor

'operatorfshall direct or evaluate the activities of at

least'10 control manipulations during his license term. These control manipulations will1normally be

performed on the VEGP simulator.

-Amend. 10 9/84 13.2.1 Amend. 16 4/85.

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

all other items shall be performed on a 2-year cycle (once each 2 calendar years).

• 1. Plant or reactor-startups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.

2. Plant shutdown.

• 3. Manual control of steam generators and/or feedwater during startup and shutdown.

4. Boration and/or dilution during power operation.

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

• 6. Loss of coolant including:

a. Significant pressurized water reactor (PWR) steam generator leaks.

b. Inside and outside primary containment.

c. Large and small, including leak rate determination.

d. Saturated reactor coolant. response.

7. Loss of instrument air.

8. Loss of electrical power (and/or degraded power sources).

• 9. Loss of core coolant flow / natural circulation.

10. Loss of condenser vacuum.

11. Loss of service water.

12. Loss of shutdown cooling.

13. Loss of component cooling system or cooling to

.an individual component.

Amend. 10 9/84 13.2.1-8' Amend. 16 4/85

VEGP-FSAR-13

- 14. Loss of normal feedwater or normal feedwater system failure.

• 15. Loss of all feedwater (normal and emergency).

16. Loss of protective system channel.

17. Mispositioned control rod or rods (or rod drops).

18. Inability to drive control rods.

19. Conditions requiring use of emergency boration.

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

21. Turbine or generator trip.

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

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,Ethe superintendent-operations, manager of unit operations, deputy general manager, and generla manager. 'Jul unsatisfactory result on the evaluation 13.2.1-9' Amend.-16 4/85

VEGP-FSAR-13 shall require the operator to have on-the-job training in areas determined as weak.

To. remain on active status, a reactor operator or-senior reactor operator is required to have a minimum of 8 h/ quarter active participation in operation of the plant or the.VEGP simulator.

C. Plant Changes Each licensed operator will'be kept informed of significant plant design changes, procedure changes, and license changes. Changes of a magnitude requiring detailed explanation will be reviewed byfD special irnbucb,o % lecture with 100 percent -tt;r. dance of licensed personnel. CPa'hcipat(6st D. Procedures Each licensed operator will review abnormal and emergency procedures at a minimum of once per calendar '

year. Failure to complete a procedure review will require that the licensee be removed from license duties until such review is completed.

13.2.1.3.2.3 Evaluation.

1 A. Observation The performance of licensed operators will be evaluated annually by operating supervision or by a-certified instructor usually on the VEGP simulator.

This shall include evaluation of actions taken or to be taken during actual or simulated abnormal or emergency conditions. ' Observation reports-are required for' personnel (supervisory and nonsupervisory)'who hold an NRC license, with the-exception of the superintendent-operations, manager of-unit ~ operations, deputy general manager, or general manager, and certified simulator instructors.

B. Annual Examinations Annual' written examinations will be given to all licensed personnel to determine areas in which requalificationitraining 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

~o perator from required attendance at requalification-13.2.1-10 Amend. 16 4/85-

VEGP-FSAR-13 lectures pertinent to that section. Any section grade 7

less than 80 percent but greater than 70 percent will require attendance at'requalification lectures pertinent to that section within 12 months from the

'~

examination date.

An overall grade of less than 80 percent correct on an annual written examination, a section grade-of less than 70 percent, or an unsatisfactory performance evaluation will require an operator or senior operator l to.be relieved of licensed duties so that he may

. participate in an accelerated requalification program.

This will be documented with written notification to the individual and to the_ appropriate department head.

An operator or senior operator who has been relieved may return to his-licensed duties following completion

of accelerated.requalification training in areas where .

he was weak, including a grade of not less than 80 percent correct on examinations given over such areas.

The NRC may participate in the annual examination process. Annual examinations will be given at.the c conclusion of the requalification training-program so as to measure the overall effectiveness of the complete

. program and not to disrupt shift manning and training schedules.

-C. Lecture Examinations f

Written examinations.will be given to individuals who received less than 80_ percent on the pertinent section of the' annual examination covering material-presented in the program lecture series. A grade of less than 80 percent on any required lecture series examination shall require a_ licensed operator to be rescheduled 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-modifications may be-documented by attendance record.

~

13.2.1.3.3: -Instructor Qualification and Requalification Program The qualification and~requalification program for instructors as described below includes requirements of.NUREG-0737, item.

. I.A.2.3. This program will be fully implemented prior to fuel

- load.

'13.2.1-11 Amend. 16 4/85

VEGP-FSAR-13 A. Initial Qualification The training department will use a qualification checklist to establish the initial qualification requirements for all new instructors and for instructors whose teaching responsibilities are going to significantly change. These special qualification checklists shall include the following requirements:

1. The instructor's supervisor will review the employee's background and establish qualification goals and qualification deadlines. Besides other qualifications, the following minimum goals will be established:

a. For new instructors who do not have a classroom teaching background, the employee will have to present a lecture to a group of 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 simulator courses to licensed operators, they will demonstrate their competence by successful completion of a senior reactor operator examination.

B. Certified Instructor Requalification Licensed or certified instructors will complete the requirements of the licensed operator requalification program annually by teaching, performing, or taking

, examinations for each required element of the requalification program. Conducting simulator training will be considered the same as supervising license duties in the plant control room. If an Amend. 7 5/84 13.2.1-12 Amend. 16 4/85

VEGP-FSAR-13 instructor is_not involved in the preceding requalification program, he may. renew his

-certification by preparing for and taking or conducting a comprehensive audit examination.

Instructors who fail'to complete these annual instructor requalification requirements will not teach integrated plant response to licensed students until

.they renew their certification.

0366V- 13.2.'l-13 = Amend. 7 -~5/84 C

y_

VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 1 OF 3)

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

Minimum

~ Description Type Integral Duration

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

. 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 Classroom or 1 week self-study Procedures 1-for

-design and operating changes

Reactor coolant system mechanical-design Reactivity: control' ~ '

mechanisms and.

indications Reactor safety.

. systems Amend.--4 2/84 Amend. 10 9/84' Amend.' 16 4/85-

VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 2 OF 3)

Minimum Description Type Integral Duration Emergency and reserve systems Containment and shielding Radiation monitoring system Auxiliary systems Radioactive waste VEGP license and Classroom or 1 week technical specifi- self-study cations License conditions and limitations

, Design limitations Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator Control room opera- 4 weeks tions (including 80 h General operating X X VEGP/ simulator) characteristics Specific operating X X

. characteristics Load changes- X X Operating limita- X X tions Standard,. emergency, X X and plant pro-cedures control manipulation X Transients X d

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

r.. ,

VEGP-FSAR-13 TABLE 13.2.1-1 (SHEET 3 OF 3)

Minimum Description Type Integral Duration Mitigating core Classroom or 1 day damage self-study Incore instrumen-tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation monitor-ing Gas generation Observation training including walkthrough Prior to achieving VEGP 3 weeks 20% power 'O'

'After achieving 'I VEGP 3 months 20% power _

Review and audit 1 week

a. Applicants who have previously been Nuclear Regulatory Commission licensed or certified will complete 3 weeks of VEGP-walkthrough training.

~b. Applicants who have previously held an SRO license will not

~

be required to complete the 3. months'of observation training.

They will complete 3 weeks VEGP_walkthrough training instead.

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

VEGP-FSAR-13 TABLE 13.2.1-2 (SHEET 1 OF 3)

LICENSED'S,ENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH OTHER THAN PWR LICENSE OR NRC CERTIFICATION  ;

, (ANY SUPERVISOR OR STAFF POSITION)

Minimum Description Type Integral Duration

' Nuclear power plant Classroom or 1 week theory self-study

. Fundamentals-of '

reactor theory General core design Radiological' safety and radiation hazards Heat transfer, fluid flow, and thermody-namics Fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convection, and radintion Change of phase -

boiling Burnout and flow instability Reactor heat transfer limits i

VEGP systems and Classroom or 4 weeks procedures self-study .

Procedures for.

design and operating changes Reactor coolant-system-mechanical

-design Reactivity control, mechanisms-and

' indications-Amend. 4 2/84 Amend. 7 5/84 1

Amend. 10_9/84 Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.2.1-2 (SHEET 2 OF 3) n Minimum Description Type Integral Duration Reactor safety Classroom or 4 weeks systems .

self-study Emergency and reserve systems Containment and

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

core alterations self-study Facilities and procedures Classroom Simulator-Control room opera- 5-weeks.

tions (including 100 h General operating- X X. VEGP/ simulator) characteristics i Specific operating X X characteristics Load changes X X .

Operating limita - X X tions Standard, emergency, .X X and plant pro-cedures Control manipulation X Transients- X Amend. 4 2/84 Amend.L10 9/84-Amend. 16 4/85

VEGP-FSAR-13 TABLE 13.2.1-2 (SHEET 3 OF 3)

Minimum Description Type Integral Duration Mitigating core Classroom or 1 day damage self-study Incore instrumen -

tation e Excore11nstrumen-tation Vital instrumen-tation Primary chemistry Radiation monitor-ing Gas generation Observation training"i' VEGP 3 months' including walkthrough

-training i

Review and audit 1 week i

.)

\ N.\ .

t pb";.ces&

a. Prior.tol achieving 20 ' power, applicants for cold licenses shall have 6 weeks of hot participation experience-as defined by Generic Letter 84-16 at a same type plant. In addition, applicants will have at least 6 weeks of VEGP shift experience which includes walkthrough training.

Amend. 4 2/84

-Amend. 10:9/84 Amend. 16 4/85 m ,v

VEGP-ESAR-13 TABLE 13.2.1-3 (SHEET 1 OF 3)

LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH 1 YEAR OF MILITARY PWR EXPERIENCE AS A REACTOR OPERATOR, ENGINEERING WATCH SUPERVISOR, OR ENGINEERING WATCH OFFICER (ANY SUPERVISOR OR STAFF POSITION)

Minimum Description Type Integral Duration Nuclear power plant Classroom or 3 weeks theory ,

self-study Fundamentals of reactor theory General core design Radiological safety and radiation hazards Heat transfer, fluid

' flow, and thermody-namics Fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convention, and radiation Change of phase -

boiling Burnout and flow instability

. Reactor heat transfer limits VEGP systems Classroom or 41 weeks self-study Procedures for design and operating changes Reactor coolant system mechanical design

-Reactivity control mechanisms and indications Amend. '4-2/84' Amend. 7'5/84 Amend. 10 9/841 Amend. 16:4/85

VEGP-FSAR-13 TABLE 13.2.1-3 (SHEET 2 OF 3)

Minimum Description Tyne Integral Duration Reactor safety systems Emergency and reserve systems Containment and shielding Radiation monitoring system Auxiliary systems Radioactive waste VEGP license and Classroom or 1 week technical specifi- self-study cations License conditions and limitations Design limitations Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom simulator.

Control room opera- 5 weeks tions- (including 100 h General operating X X VEGP/ simulator) characteristics Specific operating X X-characteristics Load changes _ X X Operating limita . X X tions Standard, emergency, X X and plant pro-cedures Control manipulation X Transients X Mitigating core Classroom or 1 day damage self-study _

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

VEGP-FSAR-13 4.

TABLE 13.2.1-3 (SHEET 3 OF 3)

Minimum Description Type Integral Duration Incore instrumen-tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation monitor-ing Gas generation Observation training'd' VEGP- 3 months including walkthrough training.

Review and audit 1 week l

. a. -Prior to VEGP. achieving 20 percent power, applicants for cold licenses shall have 6 weeks of hot participation experience as defined by Generic Letter 84-16 at a same type plant. In addition, applicants will have at.least 6 weeks of VEGP shift experience which includes walkthrough training.

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

r. -

VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 1 OF 3)

LICENSED SENIOR OPERATOR ONSITE TRAINING SYLLABUS - PERSONNEL WITH DEGREE IN ENGINEERING OR APPLICABLE SCIENCES (ANY SUPERVISOR OR STAFF POSITION)

Minimum Description Type Integral Duration Nuclear power plant Classroom or 5 weeks

. theory self-study Fundamentals of

reactor theory General core design Radiological safety and radiation hazards Heat' transfer, fluid flow, and thermody-namics Fluids and matter 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 Classroom or 6. weeks self-study Procedures for

' design'and operating changes Reactor coolant system mechanical design Reactivity control mechanisms and indications Amend. 4 2/84 Amend. 7 5/84 Amend.- 10 9/84' Amend. 16 4/85

m. . . - - ,

VEGP-FSAR-13 TABLE 13.2.1-4 (SHEET 2 OF 3)

Minimum Description Type Integral Duration Reactor safety systems Emergency and reserve systems Containment and shielding Radiation monitoring system Auxiliary systems Radioactive waste VEGP license and Classroom or 1 week

' technical specifi- self-study cations License conditions and limitations Design limitations Fuel handling and Classroom or 3 days core alterations self-study Facilities and procedures Classroom Simulator Control room opera- 5 weeks tions (including 100 h General operating .Xf X ~ VEGP/ simulator)

- characteristics Specific operating X X characteristies Load changes X X Operating limita- X X tions Standard,. emergency, X X and plant pro-cedures

~ Control manipulation.

~X ,

Transients ~ ~X .j i

Mitigating core- .. Classroom or: 1 day  ;

damage self-study.

,Incore instrumen-tation l

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

_ ._ _ . -- 1

VEGP-FSAR-13 TABLE 13.2.1-4~(SHEET 3 OF 3)

Minimum Description Type Integral Duration Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation monitor-ing Gas generation Observation training'8' VEGP 3 months including walkthrough training Review and audit 1 week a

a. Prior to VEGP achieving 20 percent power, applicants for cold-licenses shall have 6 weeks of hot participation experience-as defined by Generic Letter.84-16 at a same type plant. In addition, applicants will have at least.6 weeks of VEGP shift experience which includes walkthrough training. .

Amend. 4 2/84' Amend.J10 9/84 Amend. 16 4/85

s i-I l

VEGP-FSAR-13 TABLE 13.2.1-5 (SHEET 1 OF 3)

LICENSED OPERATOR.ONSITE TRAINING SYLLABUS (PLANT OPERATOR OR ASSISTANT PLANT OPERATOR)

, Minimum

! . Description Type Integral Duration Nuclear power plant Classroom or 12 weeks theory self-study Mathematics L Fundamentals of j reactor theory General core design Reactor and health physics and radio-  ;

logical safety l Materials l Heat transfer, fluid i flow, and

thermodynamics

' Fluids and matter Fluid statics Fluid dynamics Heat transfer by conduction, convention, and l radiation l

Change of phase -

i boiling Burnout and flow l instability Reactor heat transfer limits VEGP systems for Classroom or 12 weeks .

electrical and- self-study l reactor control Reactor coolant system mechani-cal design Reactivity control mechanisms.and l indicators l Reactor safety l systems Amend. 4 2/84 Amend. 10 9/84 l Amend. 16 4/85 l

VEGP-FSAR-13 TABLE 13.2.1-5-(SHEET 2 OF 3)

Minimum Description Type Integral Duration Emergency and reserve systems Containment shielding Radiation monitoring systems Auxiliary systems Classroom Simulator Control room 6 weeks operations. (including 100 h General-operating X X VEGP/ simulator) characteristics Load changes X X Operating limita- X X tions Standard, emergency, X X and plant pro-

cedures Control manipu- X lation Transients X Mitigating core Classroom or 1 day damage self-study-Incore instrumen-tation Excore instrumen-tation Vital instrumen-tation Primary chemistry Radiation moni-toring Gas generation Amend. 4 2/84-Amend. 10 9/84 Amend. 16 4/85

e -

i VEGP-FSAR-13 l TABLE 13.2.1-5 (SHEET 3 OF 3)

Minimum

Description Type Integral Duration i

j Observation training'B' VEGP 3 months l including walkthrough -

! training Review:and audit 1 week l

l

[

l 7 yEG P

a. Prior tolachieving 20 percent,~ applicants for cold licenses will complete observation' training at a comparable licensed commercial' nuclear power plant for a period of 6 weeks. In l addition, applicants Lwill have at least 6 weeks of'VEGP shif t-experience which includes walkthrough. training.

' Amend. 4 2/84 Amend. 10 9/84 0366V Amend. 16 4/85 L . . _

JAN 81 JUL 84 JAN 85 APR 86 JUL 86 SRO = senior reactor i

TO TO TO TO TO operator JUN 84 DEC 84 MAR 86 JUL 86 SEP 86 RO = reactor operator n o r- r- m 7 Initial Classroom y j 5' M' j { NLO = nonh.eensed Training SRO 18 :n RO 18 y !E r- operator (Fundamentals, Systems) g NLO 18 g *g { ,

Simulator SRO 18 E.c RO 9  !- RO*9 l

= ll

=- { students expected to complete future trammg.

Hot Participation ' SRO'4 { ** Sufficient operators (Extra Man on Shift)

SRO 10 RO 12- j' RO'6

~

[j.

~

{

n v a fo SRO 18 R Review and Audit N O 18 NRC License Exam 1

SRO*9 1" SRO'9

• RO*9 RO'9 Technical Specification Minimum Staffing 1 Unit Operation 2 Unit Operation (Maximum Staffing for 6 Shifts) (Maximum Staffing for 6 Shifts) Available Personnel Senior reactor operator (including shift technical 18 18 18 advisors)

Reactor operators 12 18 18 Nonlicensed operators 12 18 18 Amend. 16- 4/85 voGTLE VEGP UNITS 1 AND 2 ELECTRIC GENERATING PLANT OPERATIONAL TRAINING GeogiaNwer UNIT 1 AND UNIT 2 _ _

FIGUPE 13.2.1-2__

3685-0

. . . ~ .

i I

.)- GENERAL MANAGER '

MANAGER NUCLEAR TRAINING j

\

I I l ____________; j SUPERINTENDENT NUCLEAR TRAINING sno DRAFTSMAN CLERK I I SUPERVISOR SIMULATOR OPERATIONS MODIFICATION TRAINING SUPERVISOR sno l i

l SIMULATOR $1MULATOR' PLANT INSTRUMENT ENGINEER INSTRUCTOR ENGINEER TECHNICIAN sno sno I I SUPERVISOR SUPERVISOR PLANT HP/ CHEMISTRY TRAINING TRAINING

.)

l I I I I METHODS AND SENIOR METHODS METHODS AND SENIOR METHODS TRAINING AND TRAINING TRAINING AND TRAINING SPECIALIST

• SPECIALIST SPECIALIST' SPECIALIST 105013-mD32)

, LEGEND:

l i SRO Senior reactor operator licensed or certified.

! ' Methods and training specialists will have e sperience in electrical or mechnical maintenance, instrumentation and controls technology, or health physics and chemistry.

Amend. 16 4/85 VOGTLE  ! VEGP TRAINING ORGANIZATION 1 Georeia U

Power ELECTRIC GENERATING PL ANT i UNIT 1 AND UNIT 2 I FIGURE 13.2.1-1 36050 m

l 1

l DOCUMENT

SUMMARY

• • • • • • • • • • • • • • • • • • • • u a A A A A A A A A A A A A A A A;. A A A A A A A A A A A A A A;;. A A A A A A A A A A A A A A;. A A A;.i. A A A A;.

AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA A AA A A AAAA A AA A A AAA A AAA A AAA A AAAAAA AA A AAA AAA AAA A AA A AAA AA AA A AAA A AAAA A AAAAAAAAAAAAAAA DOCUMENT ID: 0140V DOCUMENT NAME: FSAR 13.2.2 Vogtle OPERATOR: Doris Hill AUTHOR: Valekis, J.

DATE: 03/19/85 NOTES: Amend. 10 ( Amend. 16)

AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA A AAAA AAA AAAA A A AAA A AAA A A A A A A AAA A A A AAAAA AA AAA A AAA A A AAAA AAA AA AAA AAA AAAA AAAAAA AAAAA A AAA A A A A A AA AAAA AAAA A AA A A AA A A AAAA AA AAAAAAAAAA A AAA AA AAAA AAAAA A AA AA AAAAA AAAAA AAAAA AA PLEASE RETURN THIS TITLE PAGE WITH ALL FUTURE REVISIONS

r VEGP-FSAR-13 13.2.2 TRAINING FOR NONLICENSED PLANT STAFF The VEGP staff will consist of individuals with significant differences in previous education, training, and experience.

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

Personnel will either meet the minimum education and experience recommendation of ANSI /ANS 18.1-1971 or complete a qualification program which will demonstrate their ability to perform the specific tasks. The organization conducting the training for the nonlicensed plant staff is the same as that for the licensed plant staff and is shown in figure 13.2.1-1.

13.2.2.1 Training Program A training program has been established for each VEGP organizational group. At the time of fuel load, personnel assigned to a particular group will complete the initial training before performing independent tasks or will meet the minimum education and experience required by ANSI /ANS 18.1-1971. The training programs will be the same before and after initial fuel load. On-the-job training will be used to supplement the indicated classroom instruction as necessary to prepare individuals for their assigned responsibilities.

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

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

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

e A previous course of instruction has been completed which contained the same topics and was at least the duration of the course being waived. The course may have been completed at VEGP or another facility. For example, a trainee who completes a course of instruction at Plant Hatch meeting the above criteria would not be required to repeat the course at VEGP.

e A previous course of instruction has been completed which contained all of the objectives of the course being waived. This would be determined by comparison of the objectives of the course completed and the course being waived. If the already completed course of instruction did not meet all required objectives, these additional topics may be taught and course completion may be granted.

13.2.2-1 Amend 16 4/85 m

VEGP-ESAR-13 o Completion of an examination by the trainee which is

-equivalent to a course final comprehensive examination.

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

Training programs for the following organizational groups have been established:

Health physics / radiochemistry 13.2.2.1.1 Instrumentation and controls 13.2.2.1.2

. Mechanical maintenance 13.2.2.1.3 Electrical maintenance 13.2.2.1.4 Shift technical advisor 13.2.2.1.5 Nonlicensed operator 13.2.2.1.6 Licensed operator 13.2.1 Training (instructor qualification) 13.2.2.1.7

, General employee training 13.2.2.1.8 Fire team training 13.2.2.1.9 Quality control 13.2.2.1.10 Engineering and technical support 13.2.2.1.11 The syllabus for each training program, including the duration and the organizational group receiving the training, is described in the following subsection or paragraphs.

13.2.2.1.1 Health Physics / Radiochemistry Training Program A. Initial Training Technicians who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training, pressurized-water reactor-(PWR) systems, balance of plant (BOP) systems, and mitigating core damage training normally within 12 months after assignment to the position. Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific tasks.

13.2.2-2 Amend 16 4/85

VEGP-FSAR Approximate Curriculum. outline Duration General employee badge and health 6-10 hi

• physics training Industrial safety and first aid 4h New employee-fire training 2h General pressurized water reactor 1 week systems-General balance of plant systems 1 week Nuclear physics fundamentals 2 weeks Radiation protection 1 week Chemistry fundamentals 1 week Mitigating core damage (commensurate 2h with responsibilities)

On-the-job training 1 week B. Continuing Training One of the following listed programs or other specific programs as requested by the health physics superintendent will be conducted annually. Personnel who have not completed the offered course will normally attend.

Approximate Curriculum Outline Duration Advanced health physics 1 week Analytical chemistry 1 week Radiochemistry 1 week Corrosion 16 h-C. Annual Requalification Training or Exemption Testing Health physics / chemistry technicians will complete annual _requalification training or exemption testing to make them aware of and review important_ changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

D. Initial. Foreman Qualifications (and Student Engineers)

Foremen who meet the requirements of ANSI /ANS 18.1-1971 Will complete General' Employee Training, PWR systems, BOP systems, and mitigating core damage training as i a. Duration. depends on whether the individual attends additional

' radiation worker training _as described in paragraph 13.2.2.1.8.A.

. Amend 4 2/84 13.2.2-3 _ Amend 16 4/85

VEGP-FSAR-13 described above under initial training within 12 months after assignment to the position. Those who do not meet the above requirements must complete initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

E. Continuing Foremen Training One of the listed continuing training programs or other specific programs as requested by the health physics superintendent will_be presented annually. Foremen-will normally attend these continuing training sessions unless they have already completed the offered course.

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

G. Incumbents and 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 qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements.

13.2.2.1.2 Instrumentation and Controls Training Program A. Initial Training Technicians who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training, PWR systems, BOP systems, and mitigating core damage training normally within 12 months after assignment to the position. Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific tasks.

Amend. 4 2/84 Amend. 7 5/84 13.2.2-4 Amend. 16 4/85

b }

VEGP-ESAR-13 Approximate f Curriculum Outline Duration General' employee badge and health 6-10 h'd*

L physics training Industrial safety and first aid 4h _,

New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Process fundamentals 1 week

. Mitigating core damage (commensurate 2h with. responsibilities)

On-the-job training 1 week l

{ B. Continuing Training i

One of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually. Personnel who have not j completed the offered course will normally attend.

l Approximate Curriculum Outline Duration I Electronics review 1 week Test equipment .

2 days Process instrumentation 1 week

[ 1 week Process control systems Annual Requalification. Training or Exemption Testing.

C.

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

D. Initial Foremen Training (and Student. Engineers)

Foremen who meet the requirements.of ANSI /ANS 18.1-1971 will complete General Employee Training, PWR systems, I

a. Duration depends on whether the individual attends additional radiation 1 worker training as described in paragraph 13.2.2.1.8.A.

Amend. 4 2/84 13.2.2-5 Amend. 16 4/85 t

b

VEGP-FSAR-13 BOP systems)and mitigating core damage training as described above under initial training within 12 months after assignment _to the position. Those who do not meet the above requirements must complete initial training and progress through most of the~ continuing training courses in order to demonstrate their ability to perform the specific tasks.

E. Continuing Foremen Training One of the-listed continuing training programs or other specific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend these sessions unless they have already completed the offered course.

F. Instrumentation and Controls Maintenance Supervisor Qualifications and Training The maintenance supervisors will have the qualifications required of maintenance foremen and will normally attend a similar continuing training program. After initial appointment to the position, the new supervisor will complete the following training.

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

G. Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the-instrumentation and controls career path, provided.the maintenance superintendent certifies that the' employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements.

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

~

VEGP-FSAR-13 13.2.2.1.3 Mechanical Maintenance Training Program A. . Initial, Training Maintenance-personnel who meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training, PWR systems, and BOP systems training normally within 12 months after assignment to the position. Those who do not meet the above requireme'nts-must complete initial training in order to demonstrate their ability to perform the specific tasks.

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

Industrial safety and first aid 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Maintenance fundamentals 1 week Mechanical' fundamentals 1 week On-the-job training 1 week B. Continuing Training One.of the following listed programs or other specific programs as requested by the maintenance superintendent will be conducted annually. Personnel who have not-completed the offered course will normally attend.

Approximate Curriculum Outline Duration

' Theory and maintenance of. pumps 1 week .

and valves Power transmission devices 2. days Shop fundamentals 1 week Crane safety and operation 3 days Shaft alignment 2 days Motor-operated valves- 3 days

a. Duration depends on whether the individual attends-additional radiation-working training as described in paragraph.

13.2.2.1.8.A.

13.2.2-7 Amend.116 4/85 e

k VEGP-FSAR-13 C. Annual Requalification Training or Exemption Testing Mechanics will complete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

D. Initial Foremen Training (and Student Engineers)

Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete General Employee Training, PWR cystems, and BOP systems training as described above under initial training within 12 months after assignment to the position. Those who do not meet the above requirements must complete initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

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

specific programs as requested by the maintenance superintendent will be presented annually. Foremen will normally attend those continuing training programs unless they have completed the offered course.

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

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

Approximate Curriculum Outline Duration Electrical, pressure vessely and 3 days piping codes and standards 4 (including nondestructive testing review)

. G. Incumbents and New Employees

. Personnel with experience that exceeds NRC commitments may fill a position in the mechanical career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed 13.2.2-8 ' Amend. 16 4/85 )

i I

VEGP-FSAR-13 the position requirements. The training department maysalso accept prior training or experience to fill k specific course requirements.

13.2.2.1.4 Electrical Maintenance Training Program A. Initial Training _

Maintenance personnelLwho meet the education and experience requirements of ANSI /ANS 18.1-1971 will complete general employee training, PWR systems,tand BOP systems training normally within 12 months,after . _

assignment.to the position._ Those who do not meet the above. requirements must complete initial training in order-to_ demonstrate their ability _to perform the specific' tasks.

Approximate Curriculum Outline Duration General employee badge training 6-10h'kl 4h Industrial safety and'first aid New employee fire training 2h General pressurized water reactor ~ 1 week systems-General balanceJof plant systems 1 week Maintenance fundamentals 1 week Direct current fundamentals 1 week Alternating current fundamentals 2 weeks Electrical safety, drawings, and 1 week-test' equipment On-the-job training 1 week B. ~ Continuing Training One of the following listed programs or other specific programs as requested by the maintenance superintendent-will be conducted annually. Personnel who have not

. completed the offered course;will-normally attend.

a$ Duration depends on whether the. individual attends additionali radiation worker trainingLas described in paragraph:

13.2.2.1.8.A.

3 Amend. 10 _9/84

, 13.2.2-9 Amend. 16 4/85

VEGP-FSAR-13 Approximate Curriculum Outline Duration Protection devices, control devices, 3 days and motor control centers ac/dc motors and generators 4 days Solid state theory 3 days Batteries, chargers, and inverters 1 day Pyrotronics fire detectors 1 day Motor-operated valve maintenance 1 day Switchgear and breaker maintenance 3 days Amp lugging i day C. Annual Requalification Training or Exemption Testing Electricians will comr1.ete annual requalification training or exemption testing to make them aware of and review important changes made to plant emergency and disaster, radiation protection, security, and respirator procedures.

D. Initial Foremen Qualifications (and Student Engineers)

Foremen who meet the requirements of ANSI /ANS 18.1-1971 will complete general employee training, PWR systems, and BOP systems training as described above under initial training within 12 months after assignment to the position. Those who do not meet the above requirements must complete. initial training and progress through most of the continuing training courses in order to demonstrate their ability to perform the specific tasks.

E. Continuing Foremen Training One of the listed continuing training programs or other specific programs an requested by the maintenance superintendent will be presented annually. Foremen will normally attend continuing training programs unless they have previously completed the offered course.

F. 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 positiong the new supervisor will complete the following ~'

training.

13.2.2-10 Amend. 16 4/85

VEGP-ESAR-13 Approximate Curriculum Outline Duration Electrical, pressure vessel, and 3 days piping codes and standards (including nondestructive testing review)

G. Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the electrical career path provided that the maintenance superintendent certifies that the employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements.

13.2.2.1.5 Shift Technical Advisor Training Program A. Education Requirements 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 technical advisor training program described in table 13.2.2-1.

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.

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

Persons not actively performing the shift technical

, advisor functions for a period of 4 months or longer shall, prior to assuming responsibilities of the position, as a minimum receive training to ensure they are cognizant of facility / procedure changes ~that occurred during their absences.

13.2.2-11 Amend. 16 4/85

VEGP-FSAR-13 Persons not performing the shift technical advisor function ~for a period of 6 months or longer shall, prior to assuming the responsibilities of the position, undergo an individual requalification program.

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

Approximate Curriculum Outline Duration General employee badge and health 6-10 h<a>

physics training Industrial safety and first aid 4n -

New employee fire training 2h Nuclear power plant fundamentals 1 week Power plant components 1 week VEGP systems 4 weeks On-the-job training 1 week B. Continuing Training After completing initial qualifications, the nonlicensed operator will complete qualification on the plant systems on which he was not initially qualified. Normally, the nonlicensed operator will qualify on all-systems outside the control room and .

containment during the individual's first 3 years in the plant operations. department.

'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.

Amend. 3.1/84

(, ' #A~~

g' p Q* 13.2.2-12 Amend.

. Amend. 16 4/85 4 2/84

1 VEGP-FSAR-13

D.- Nonlicensed' Operator Progression

. . After completing a license training program, many

. operators will progress to licensed positions. The-licensed ~ training programs are described in subsection 13.2.1.

i. ,

13.2.2.1.7~ Instructor Qualification' Program and Certified Instructor.Requalification-Program This program has been' outlined in paragraph 13.2.1.3.3 for all -

training instructors. -In addition to these requirements, the

fire protection training instructor shall also meet the j . requirements outlined in paragraphs 13.2.2.1.9.D and-9B.C.3.d(2).

1 13.2.2.1.8 General Employee Training (Badge Training)

A. General ~ Training j - All

personnel who are granted unescorted access to the VEGP's' protected' area will receive the following j training or, if they have completed a.similar program i- at another plant or facility, will be tested to verify satisfactory knowledge of VEGP procedures.

Approximate Curriculum Outline Duration I

i General description offVEGP facilities,~ general VEGP 4h procedures and instructions,

station emergency plans, I industrial safety program, fire

protection program, security

~

program, and quality assurance .

program.

4 M

q 4 a. . Duration depends on whether the. individual attends additional radiation worker training as described in paragraph- >

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VEGP-FSAR-13 Radiation health and safety 2h will meet the intent of Regulatory Guide 8.8 for personnel who enter restricted areas.

Regulatory Guide 8.27 and 8.29 are being used to develop the radiation protection portion of general employee training.

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

Approximate Curriculum Outline Duration Radiation worker training 4h Additional radiation work practices training will be provided for those personnel who are required to work in radiation-controlled areas without escort.

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

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

1

.13.2.2.1.9 Fire Brigade Training-A. Initial Training Personnel assigned to-any firn brigade will complete training in the following areas as designated by ESAR appendix 9B before being assigned as active brigade members.

13.2.2-14 Amend. 16 4/85 e__

q VEGP-FSAR-13 Approximate Curriculum Outline Duration

1. Indoctrination of the plant 4 days firefighting plan with_ specific identification of each individual's

. responsibilities.

2. Identification of the type and location of fire hazards and associated types of fires that could occur in the' plant.

3. The toxic and corrosive.

characteristics.of expected products of combustion.

4 '. Identification of the location of firefighting equipment for each fire. area, and familiariza-tion with the layout of_the plants, including. access and egress routes of each area.

5. The proper use of available firefighting equipment and the corrective method of fighting each type of fire.

The types of fires. covered' should include fires in energized electrical equip-ment, fires in. cables and cable: trays, hydrogen fires, fires-involving flammable and combustible liquids or hazardous process chemicals, fires result-ing from construction or modifi-cation-(welding), and record file fires.

6. .The proper'use of communication, lighting, ventilation, and emergency breathing equipment.

7,. The proper method for. fighting fires.inside buildings and.

confined spaces.

Amend. 1 11/83 13.2.2-15 Amend. 16 4/85-

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J VEGP-FSAR-13

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

9. Detailed review of firefighting strategies and procedures.

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

B. Periodic-Retraining

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

Refresher classroom training courses will be held for all fire brigade members every 2 years. (Refer to appendix 9B, 9.5.1C3d, sections (4) and (5).)

2. Drills Quarterly drills shall be performed, and at least one drill per year will be performed unannounced to-determine the readiness of the' fire brigade. Drills shall be repeated in sufficient frequency'to ensure that each member of the brigade participates in at least two drills per year. Further, at least once per year a drill shall be performed on a "back.

shift" for each shift brigade. (Refer to appendix 9B, 9.5.1C3d(7).)

C. Annual Practice Practice sessions will be-held at least once per year for each shift brigade on the proper methods of fighting possible plant fires, breathing apparatuses, and under strenuous conditions. Each member of the fire brigade will experience actual fire extinguishment on~an annual basis. >This may be done in the quarterly' training sessions. (Refer to appendix 9B, 9.5.1C3d, section (6).)

D. Instructor Qualification Instruction of the fire brigade will be provided by

. qualified individuals suitably trained in fighting the types of fires that could occur in the plant, using the types of equipment available in the plant.

13.2.2-16 Amend. 16 -4/85 L.__n____._______.________________________________._________________.__________.._

VEGP-FSAR-13 E. General Employee Fire Training Fire protection training for plant employees who are allowed unescourted access will include instructions in the following areas:

1. Appropriate fire protection administrative controls.

2. Fire barrier and fire barrier penetration seals.

3. Response to fire alarms.

4. Action and responsibility upon discovery of fires.

The capability to evacuate the plant facilities will be evaluated annually. This evaluation may be conducted coincidentally with emergency plan exercises or drills.

13.2.2.1.10 Quality Control Training Program A. Initial Training Quality control inspectors who meet the requirements to be certified Level I in accordance with ANSI N45.2.6-1978 will complete general employee training as described below. Those who do not meet the above requirements must complete initial training in order to demonstrate their ability to perform the specific tasks.

Approximate Curriculum Outline Duration General employee badge training 6h Industrial safety and first tid 4h New employee fire training 2h General pressurized water reactor 1 week systems General balance of plant systems 1 week Quality _ control codes, standards, 3 days and procedures Visual inspection 1 week 13.2.2-17 Amend. 16 4/85

VEGP-FSAR-13 B. Continuing Training After' completing initial qualification, quality control personnel will usually attend annually a program.to improve their quality control skills or a program from the electrical, mechanical, or instrumentation and controls schools.

C. Annual Requalification Training or Exemption Testing 2 Quality control specialists will complete annual requalification training or exemption testing to review-important changes to plant emergency, radiation protection, security, and respirator procedures.

D. Incumbents and New Employees Personnel with experience that exceeds NRC commitments may fill a position in the quality control career path

, provided the general manager certifies that the employee's experience qualifications exceed the position requirements. The training department may also accept prior training or experience to fill specific course requirements.

.l 13.2.2.1.11 Engineering and Technical Support A. Initial Orientation Training Professional personnel who do not have prior nuclear power plant experience will complete the following orientation program normally during the first 6 months at VEGP.

Approximate

. Curriculum Outiftg Duration .

General employee badge and health 6h physics training Industrial safety and first aid 4h New employee fire training 2h Reactor theory, health physics,. 1 day and primary systems Primary systems, emergency systems, 1 day.

heat removal systems, and radiation waste and monitoring

, systems 13.2.2-18 Amend. 16 4/85

VEGP-FSAR-13 Approximate

-Curriculum Outline Duration Heat transfer and fluid flow, 1 day

secondary systems, electrical systems, and accident analysis Nuclear instrumentation systems, 1 day nuclear control systems, integrated plant control, and simulator plant operations 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. Other personnel including the managers of the Health Physics, Chemistry, and Instrumentation and Controls Departments, as well as the plant manager'will complete training in mitigating .

core damage commensurate with their responsibilities.

Amend. 16 4/85-13.2.2-19

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l; VEGP-ESAR-13 17.2.2.4 Initial Position ' Analysis

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j. Ths training programs d scribed in section 13.2 are the result of the initial position analysis for VEGP staffing. The training organization will use a combination of plant equipment reviews'by instructors, training committee reviews by plant s porvisors, 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 feedback to meet our overall training objective to train for

, 'j ob . proficiency ,

i 13.2.2.5 Training Program Syllabus The:VEGP training organization is described in subsection 13.2.1 and figure 13.2.1-1. Georgia Power Company will use the same training programs to qualify its personnel both before and after the initial fuel loading. Almost all programs in this section are considered formal or " classroom" programs. A formal program consists of instruction in the classroom, laboratory, simulator, and field which is supervised by an instructor. Specifically, the shift technical advisor program (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.

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

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

13.2'.2.8 Fire Protection Training Program A description of.the fire protection-training program used for fire. brigade members-is described in paragraph 13.2.2.1.9.

6

! 13.2.2

~~-- ~- ,

7 4

i VEGP-ESAR-13 13.2.2.9 Training Program Effectiveness Training program effectiveness is evaluated by either written,

- oral, or practiced demonstration examinations for each employee.

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

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

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VEGP-FSAR-13 TABLE 13.2.2-1 COMPARISON OF SHIFT TECHNICAL ADVISOR CURRICULUM WITH INPO RECOMMENDATIONS Georgia Power Topic INPO(h) Company (h)

Education High school fundamentals 240 Note a College fundamentals 520 Note a Plant-specific applied fundamentals 120 120 Management / supervisory skills 40 40 Plant systems 200 200 Administrative controls 80 Note b General operating procedures 30 Note b Transients / accident 30 Note b analysis and emergency procedures Simulator training 100 100 Mitigating core damage O Note b Incore instrumentation Excore instrumentation Vital instrumentation Primary chemistry -

Radiation monitoring l

Gas generation

a. All shift technical advisors will have a bachelor's degee in g scientific or engineering discipline.

b. These topics will be incorporated into the simulator training syllabus.

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DOCUMENT

SUMMARY

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0367V DOCUMENT NAME

FSAR 13.3 Vogtle OPERA 'OR

Doris Hill AUTHOR: Jim Valekis DATE: 03/14/85 NOTES:

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VEGP-FSAR-13

~ 13.3 EMERGENCY'~ PLANNING

. A comprehensive emergency plan'for VEGP Units 1 and 2 is provided as a separate volume to this application.

I

h. S 0367V .

13.3-1 x-

DOCUMENT

SUMMARY

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VEGP-FSAR-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, Rev.2 1978, Quality Assurance Program Requirements (Operations), and ANSI N18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants.

The general manager - Vogtle nuclear operations (GMVNO) 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 and maintenance activities as part of their normal duties.

. 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 (PRB) serves as a review and advisory group to the GMVNO. The PRB reviews plant administration, maintenance, and operations.as related to nuclear safety and environmental aspects; ensures these activities are consistent with company policy-approved procedures and operating license provisions; and makes recommendations to-the GMVNO on matterst brought before it.

The PRB is composed of, as a minimum, one member of the plant staff'from those disciplinary groups listed below:

o Operations.

e Maintenance.

e -Quality Control' (QC).

e Health Physics or Chemistry.

e Regulatory Compliance.

e Plant Engineering and Services, j l

)

13.4.1-1 Amend. 16 4/85-  !

l l

VEGP-FSAR-13 Collectively, these members possess the type and degree of expertise required to review unplanned events and proposed changes to systems, procedures, tests, and experiments that affect _ nuclear safety. The chairman and vice chairman of the PRB are designated by the GMVNO. The minimum quorum of the PRB will consist of the PRB chairman or vice and four members. The PRB meets at least once per calendar month.

TheLPRB is specifically responsible for the following:

A. Review of:

1. Procedures that establish plantwide administrative controls to implement the quality assurance program or technical specification surveillance program.

2. Procedures for changing plant operating modes.

3. Emergency and abnormal operating procedures.

4. Procedures for effluent releases of radiological consequence.

5. Fuel handling procedures.

B. Review of:

1. Program required by Technical Specifications.

2. Proposed procedures and changes to procedures, equipment, or systems that involve an unreviewed safety question as per 10 CFR 50.59.

C. Review of proposed tests and experiments that involve an unreviewed safety question.

D. Review of proposed changes to the Technical Specifications.

E. Review of the report of the investigation of violations of the technical specification that covers evaluation and recommendations to prevent recurrence.

F. Review of all. reportable events.

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 Bohrd.

13.4.1-2 Amend. 16 4/85

1 VEGP-FSAR-13 I. 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 recommended changes to the GMVNO.

K. Review of any accidental, unplanned, or uncontrolled radioactive release in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci for noble gases or 0.02 Ci of-radioiodines 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 : constitutes an unreviewed safety question.

4 C. Provide written notification within 24 h 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 shall have responsibility for resolution of such disagreements.

The PRB 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.

1 0

4 0368V- 13.4.1-3 Amend. 16 4/85

DOCUMENT

SUMMARY

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1 VEGP-FSAR-13 l 13.4.2 INDEPENDENT REVIEW The Safety Review. Board (SRB) provides an independent review and audit of designated activities in the following areas:

o Nuclear power plant operations.

o Nuclear engineering.

o Chemistry and radiochemistry.

4 o Metallurgy.

o Instrumentation and control.

o Radiological safety.

o Mechanical and electrical engineering.

o Quality assurance practices.

Specifically, the SRB will review:

l A. The safety evaluations-for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59 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 10 CFR 50.59.

C. Proposed tests or experiments which involve an-unreviewed safety question as defined in 10 CFR 50.59.

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 l normal and expected performance of plant equipment '

_ that affect nuclear safety.

G. The results of the PRB's review oftall reportable l events. l 13.4.2-1 Amend. 16 4/85-

r VEGP-FSAR-13 H. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

I. Reports and meeting minutes of the PRB.

In addition, periodic audits of plant activities will be performed under the cognizance of the SRB to evaluate:

A. The conformance of pla.it operations to provisions contained within the Technical Specifications and applicable license conditions.

B. The performance, training, and qualification of the plant staff.

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.

H. Any other area of plant operation considered appropriate by the SRB or the executive vice president - power supply.

The SRB will report to and advise the executive vice president - power supply on matters related to their responsibilities.

The SRB 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 l vice president - power supply or other such person as he may i designate. No more than a minority of the SRB will be members of the onsite 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 SRB activities at any one time. Consultants may be used at the discretion of the chairman or vice chairman to

_ provide expert advice to the SRB.

13.4.2-2 Amend. 16 4/85

VEGP-FSAR-13 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 at least three SRB members. No more than a minority of the quorum will have line responsibility for operation of the plant.

Reports of SRB activities will be prepared, approved, and distributed as described below:

A. Minutes of SRB activities will be prepared and submitted to management within l' 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 management within 30 days following completion and SRB approval.

13.4.2-3 Amend. 16 4/85 Q -

l' VEGP-FSAR-13

'13.4.3 INDEPENDENT SAFETY ENGINEERING REVIEWS An independent safety engineering group (ISEG) will be established prior to initial fuel loading to perform independent reviews of plant operations with emphasis on improving plant safety.

13.4.3.1 Composition The ISEG will be comprised of a minimum of five qualified individuals who will repo'rt to the manager-nuclear operations analysis in the corporate office.

13.4.3.2 Qualifications ISEG members will have a bachelor's degree in engineering or applied science with a minimum of 1 year experience in this field, including at least 6 months nuclear experience.

13.4.3.3 Responsibilittes The ISEG will be responsible for:

A. Review of plant operating characteristics, NRC issuances, industry advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety.

B. Review-of selected plant activities including maintenance modifications,. operational problems, and operational analysis, and in the establishment of programmatic cequirements for plant activities. The

.ISEG will develop and present detailed recommendations to the appropriate level of management for improvements such as revisions to procedures ore equipment modifications.

C. ~ Maintaining surveillance of plant operations and ,

maintenance activities to provide independent verification that these activities are performed correctly, and that human errors are reduced as far as practicable. -

_ D. Providing a report of their activities at least.once per month to advise corporate management of the overall quality and safety of operations.

i 4/85 13.4.3-1 Amend. 16 l

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-13.4.3.4 Authority The authority of the ISEG will be such that:

A. The ISEG. function will be independent of the functions of the Plant Review Board and-the Safety Review Board.

-B. The ISEG will not be. responsible for sign-off functions such that it becomes involved in the operating organization.

'0370V' 13.4.3-2 -Amend. 16 '4/85.

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DOCUMENT

SUMMARY

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DOCUMENT ID: 0371V DOCUMENT NAME: FSAR 13.5.1 Vogtle j OPERATOR: Doris Hill AUTHOR: Jim Valekis DATE: 03/14/85 NOTES:

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- s VEGP-FSAR-13 13.5 PLANT PROCEDURES 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.

1;.5.1 ADMINISTRATIVE PROCEDURES Administrative procedures provide rules, instructions, policies, practices, or guidelines for the plant staff. They will be.

completed at least 6 months prior to Unit 1 initial fuel loading.

13.5.1.1 Administrative Procedure Descriptions A. Procedures for Preparation, Review, and Control of Proceduren These procedures establish the controls for the preparation, review, and control of all plant procedures. Included within these procedures are provisions to ensure that new or revised procedures are reviewed for adequacy by appropriately qualified personnel and approved for release by authorized personnel. The general manager - Vogtle nuclear operations has ultimate responsibility for all plant procedures; however, a provision is made to establish department heads'as the approving authority for those procedures covering activities within their area of responsibility. Provisions exist to ensure that changes or revisions to procedures are: reviewed and approved in accordance with the same administrative controls used for review and approval of new procedures. A provision is made to ensure that plant procedures are reviewed at least every 2 years by a knowledgeable individual to determine whether changes are necessary or desirable. Other provisions ensure

.that procedures, once approved, are distributed

-appropriately so that only the most current procedures are used by plant personnel.

B. Procedures for Making Temporary Changes to Procedures This procedure provides the method for making a temporary change to an approved plant procedure.

13.5.1-1 Amend. 16 4/85 L

VEGP-FSAR-13 Included in this procedure is a provision to ensure that any such change be approved by at least two knowledgeable members of the plant staff, one of whom shall be the on-duty operations supervisor in charge of the shift. Also included in this procedure is a provision to ensure that temporary changes to procedures are documented and incorporated as appropriate into the next revision of the procedure.

C. Procedures for Feedback of Operating Experience These procedures include measures to ensure that pertinent operating experience information that originates from both within and outside of the plant organization is feedback to operators and other appropriate personnel in accordance with NUREG-0737, item I.C.S. Included is the identification of organizational responsibilities for reviewing and prioritizing operating experience, and for ensuring distribution of pertinent information to the appropriate plant personnel. Steps exist to ensure that information is reviewed by individuals of appropriate technical knowledge and that appropriate  ;

corrective actions (such as procedure or program revisions) if needed are specified. Additional steps ensure that plant personnel do not routinely receive a large volume of operating experience that might obscure the lassons to be learned from more significant events, and also that the program receives periodic evaluation for effectiveness.

D. Procedures for Control Room Access These procedures give the shift supervisor authority to limit access to the control room to those individuals responsible for the' direct operation or support of the plant. Included are steps that direct personnel other than the onshift operations crew.and the operations-chain of command to request permission of the shift supervisor to enter the limited access area shown in figure 13.5.1-1. Also, these procedures establish good-conduct rules for personnel within the control room area to avoid any disruption of operating activity. In addition to the shift supervisor, the onshift operations supervisor or the superintendent of operations may give permission to enter the limited access area; however, responsibility for limiting

. control room access shall be a normal shift duty of the shift supervisor. These procedures address the requirements of NUREG-0737, item I.C.4, for control room 13.5.1-2 Amend. 16 4/85 l

VEGP-FSAR-13 access; while the requirements for establishing the lines of authority, responsibility, and succession in the control room are addressed by the procedures described in section E.

E. Procedures for Operating Duties, Responsibilities, and Authority These procedures clearly describe the duties, responsibilities, and authority for the control room personnel, w.ich include the onshift operations supervisor, the shift supervisor, the plant operator, the assistant plant operator, and the shift technical advisor. The command line of authority for these personnel is established by these procedures.

Specifically, the onshift operations supervisor is established as the senior operations representative on each shift and shall have responsibility for the safe and efficient operation of the plant. The shift supervisor is established as having responsibility for the safe and efficient operation of his assigned unit, since a shift supervisor is assigned to each operating unit on each shift. Included in these procedures are 4 provisions for the onshift operations supervisor to maintain a broad perspective of operational conditions affecting the safety of the plant at all times and provisions for him not to become totally involved in any single operation during plant transients or emergency conditions. Other provisions establish the onshift operations supervisor as having the authority and responsibility to declare emergencies and for functioning as the emergency director until being relieved of this responsibility by a higher ranking qualified manager.

Provisions for ensuring that the onshift operations

, supervisor is not routinely performing administrative functions that could detract from or that are cubordinate to his command function and his responsibility for ensuring the safe operation of the plant are exemplified by the following:

1. An operations supervisor who is not on shift shall prepare work and. vacation schedules.

2. The shift supervisor shall issue clearances for l equipment within his assigned unit. l i

3. The shift supervisor shall have the administrative I duty of limiting access to the control room.

I 13.5.1-3 Amend. 16~4/85

VEGP-FSAR-13 The procedures described in this section are in accordance with requirements of NUREG-0737, item I.A.1.2, item I.C.3, and item I.C.4. The process for handling standing orders is addressed in section F.

F. Procedures for Standing Orders These procedures provide for the issue of temporary instructions to plant operating personnel to address subjects not covered by existing plant operating procedures. Included in these procedures are '

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provisions for maintaining and inplementing approved standing orders, periodically reviewing standing orders for continued applicability, and ensuring that standing orders are not maintained over 1 year before deletion or conversion into a plant operating procedure.

G. Procedures for Shift Manning and Overtime Restrictions These procedures establish the normal and minimum shift positions that must be manned for operation of the plant. Included is the number of individuals to fill these normal and minimum positions for both one-unit and two-unit operation. These procedures restrict the use of overtime that may be scheduled to meet the shift crew staffing requirements, such that overtime use does not exceed the guidance provided in NUREG-0737, item I.A.1.3, as revised by NRC Generic Letter 82-12.

Additional provisions are made to ensure that the use of any overtime that would exceed the restrictions of Generic Letter 82-12 must be authorized by the general manager - Vogtle nuclear operations or the manager of unit operations; an evaluation of the excess overtime request will be documented.

H. Procedures for Shift Relief and Turnover These procedures ensure that a comprehensive exchange of information takes place between the oncoming and offgoing shift personnel so that the oncoming shift is aware of critical plant status information and system availability prior to assuming duty. Included are provisions to ensure that each oncoming individual reviews the logs, round sheets, and checklists that are applicable to his position and that he discusses important items affecting plant operation with the

. offgoing individual. Provisions also include ensuring that an individual is qualified for the position that he will assume. These procedures. establish as part of 13.5.1-4 Amend. 16 4/85 u _

I I VEGP-FSAR-13 the offgoing control room opect or responsibility the need to ensure that his relief e fully aware of existing plant conditions and )! alert, coherent, and fully capable of performing hae assigned duties. These procedures are in accordance with the requirements of NUREG-0737, item I.C.2.

I. Equipment Control Procedures These procedures provide instructions for releasing plant equipment or systems for n. .intenance, testing, or inspection; they establish the shift supervisor as the responsible authority for issuing and releasing clearances for equipment to be taken out of service within his assigned unit. The provisions of these precedures include steps to ensure that equipment taken out of service and placed in a controlled status is clearly identified by the use of tagging. Other provisions provide for a second qualified person verifying the isolation or restoration of a safety-related component or system, including proper realignment unless functional testing can be performed to prove the correct realignment of all equipment, valves, and switches involved. In cases of significant radiation exposure, a second verification of safety-related system alignment will not be made.

Additional provisions are made to maintain the status of equipment and to determine the operability of equipment upon return to service; on return to service a system lineup verification will be made and additional lineup verifications may be made at periodic intervals while in service. These procedures address the requirements of NUREG-0737, item I.C.6 and item II.K.1.10, and the requirements of ANSI N1817-1976, 4

Section 5.2.6, relative to equipment control.

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, i and requirements.

K. Fire Protection Procedures The VEGP fire protection program is governed and implemented through the use of fire protection i

13.5.1-5 Amend. 16 4/85

i VEGP-FSAR-13 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 Temporary procedures are issued as required to provide detailed instructions for specific jobs that are of a specific duration.

N. Emergency Core Cooling System Outage Data Collection Procedures These procedures are developed for collection of emergency core cooling system outage data in accordance with NUREG-0737, item II.K.3.17; this data will be reported to the Nuclear Regulatory Commission in accordance with the Technical Specifications.

O. Initial Test Program Administration Procedures The administrative procedures that establish controls for that part of the initial test program prior 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 or the startup manual.

P. Plant Security Procedures Plant security procedures provide for the implementation of the security plan. (See section 13.6.)

0371V 13.5.1-6 Amend. 16 4/85 c

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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 verifying 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 a

. qualified person performing a function or task.

Subsections of this section will vary according to procedure type. . Format for each procedure type will be consistent.

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VEGP-FSAR-13 l 5.0 ACCEPTANCE CRITERIA Procedures will contain, where applicable, acceptance criteria against which the success or failure of test type activity may be judged. This section may be omitted if none are required.

6.0 REFERENCES

' References, including reference to technical specifications, will be included in procedures as applicable.

These procedures are classified as follows:

A. Plant / Unit Operating Procedures These are procedures for integrated plant operations,-

such as mode changes.

B. System Operating Procedures These procedures are for normal, alternate means of and limits of operation of individual plant systems, including removal from service and return to service.

C. Surveillance Procedures (Operations Department Responsibility)

These are procedures which describe how to perform testing functions required to verify operational readiness of structures systems and components.

D. Annunciator Response Procedures These procedures specify responses to annunciated alarms. They outline automatic system response and operator actions to mitigate the conditions.

These procedures will be indexed by light board number and alarm window coordinates to facilitate operator response. Any annunciator response procedure providing response to an emergency condition will reference the appropriate emergency operating-procedure.

E. Abnormal Operating Procedures These procedures specify operator actions for restoring a plant operating variable to its normal controlled value when it departs from its range or to 13.5.2-2 Amend. 16 4/85 L

7 VEGP-FSAR-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, could degenerate into a condition requiring action under an emergency operating procedure.

F. Emergency Operating Procedures The emergency operating procedures are developed according to an emergency operating procedure writer's guide.

'The emergency operating procedures are developed according to action plan which incorporates

-developmental information provided in the implementation plan guideline published by the Institute of Nuclear Power Operations.

Technical guidelines (emergency response guidelines) and accompanying background / support information are supplied by the Westinghouse Owners Group. _The generic background / support information is made plant specific. In addition, each generic technical guideline is reviewed to determine the information needed to generate plant-specific procedures. An emergency operating procedures writer's guide is developed prior to generating these procedures from the Westinghouse Owners Groupftechnical 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 procedureHis 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 Amend. 16 4/85 u

i VEGP-FSAR-13  :

Use'of the Westinghouse Owners Group technical guidelines and supplemental information in accordance with the-emergency operating procedures action plan meets the intent of NUREG-0899, items;I.C.1 and I.C.8, asiclarified by NUREG-0737, Supplement 1.

G. Temporary Procedures Temporary procedures are issued as required to provide detailed instructions for specific jobs that are of a specific duration.

13.5.2.2 Maintenance Procedures The VEGP maintenance procedures'are divided into the following categories:

A. Generic Procedures These procedures, which are' general in nature, cover maintenance activities that can be performed on many different pieces of equipment or instrumentation, i.e.,. vibration analysis, inspections, insulation

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resistance checks, calibrations, functional tests, etc.

B. Specific Maintenance Activity Procedures

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These procedures give instructions for service, repair, calibration, or functional testing of specific pieces of equipment,-components, or instrumentation.

C. Surveillance Procedures These procedures describe how to perform testing

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functions or parts-replacement, as required to verify the operational readiness of-structures, systems, components, and instrumentation.

D. Special Procedures Procedures for the maintenance, repair, calibration and functional' testing of health physics,. fire protection,-and security equipment are also provided.

These-procedures will-be completed approximately 6' months prior to fuel loading. The maintenance department-has

.-responsibility-for work performed in accordance with these procedures. Plant maintenance and modifications are also governed by1 administrative procedures.

Amend. 8 7/84-13.5'2-4 Amend. 16- 4/85

n 1 VEGP-FSAR-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 the 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 guidelines for tests, analyses, additions,.or dilutions with respect to plant chemistry and radiochemistry. The health physics and chemistry laboratories ara-responsible for performing these activities.

C. Refueling Procedures 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.

0372V- 13.5.2-5 Amend. 16 4/85 L