ML19322A759

Chapter 12 of Oconee 1,2 & 3 PSAR, Conduct of Operations. Includes Revisions 1-6

ML19322A759
Person / Time
Site:	Oconee
Issue date:	12/01/1966
From:	DUKE POWER CO.
To:
References
NUDOCS 7911210783
Download: ML19322A759 (18)

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TABLE OF CONTENTS i

Section a Page 12 CONDUCT OF OPERATIONS 12-1 12.1 ORGANIZATION AND RESPONSIBILITY 12-1 12.1.1 FUNCTIONAL DESCRIPTION 12-1 ,

-12.1.2 QUALIFICATIONS 12-2 1 12.1.3 ORGANIZATION DIAGRAM 12-2 12.2 TRAINING 12-2 1 12.2.1 STATION STAFF 12-2 12.2.2 REPLACEMENT PERSONNEL 12-5 12.2.3 ON-THE-JOB TRAINING 12-5 12.2.4 EMERGENCY DRILLS 12-5 0 12.3 WRITTEN PROCEDURES 12-6 12.4 RECORDS 12-6 12.5 ADMINISTRATIVE CONTROL 12-6 A

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O LIST OF FIGURES Figure Title 12-1 Steam Production Department, Organization Chart 12-2 Station Organization Chart l

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12 CONDUCT OF OPERATIONS 12.1 ORGANIZATION AND RESPONSIBILITY 12.1.1 FUNCTIONAL DESCRIPTION The Steam Production Department of Duke Power Company has direct line respon-sibility for all fossil and nuclear production operations. Centralized con-trol over all of these operations is maintained by t Office in Charlotte, North Carolina, headed by er A g eg rtg ing General

= Prer# dent Steam Production, and a staff experienced in all phases of conventional and nuclear station operation. Figure 12-1 shows this' organization. Available to this department for consultation and advice on a day-to-day basis are the other departments of the Company. Each station functions as an independent unit with assistance from the General Office staff as needed. Under super-vision of the General Office Steam Production Department, the Station Superintendent is responsible for safe, reliable and efficient operation of his plant.

The Oconee Nuclear Station organization as shown by Figure 12-2 will consist of approximately 66 full-time employees functioning in three main groups:

Operation, Maintenance and Technical Support.

The normal operating shift will be one Shift Supervisor, one Control Operator, one Assistant Control Operator and one Utility Operator. The Shift Super-O visor will report to the Operating Engineer and his assistant.

The maintenance force will consist of approximately 18 men experienced in mechanical and electrical maintenance of large steam-electric generating stations and/or nuclear stations under a Maintenance Supervisor and an assistant. This number of men will be adequate for normal maintenance, but will be supplemented by maintenance men from other power stations for large conventional maintenanca jobs such as turbine-generator inspections.

The Technical Support Group will consist of a Technical Support Engineer and a staff of approximately 20 engineers and technicians who will function in the areas of reactor physics, conventional chemistry, radiochemistry, radio-logical protection, station performance and maintenance of instruments and controls.

The initial start-up including acceptance tests, initial core loading, initial criticality and approach to full power commercial operation will be performed by the Oconee regular staff with assistance in physics testing and l other areas from The Babcock & Wilcox Company, Bechtel Corporation and the Steam Production Department General Office staff as needed. For core loading and initial criticality, cold (pre-critical) Senior Operator licenses will be obtained for the Operating Engineer, his assistant and the five Shif t Super- l visors. Cold (pre-critical) Operator licenses will also be obtained for the five Control Operators. After an initial operating period sufficient for necessary training, Operator licenses will be obtained for additional shif t personnel and Senior Operator licenses for engineering personnel as required.

, The personnel assigned to the station and their organization will be essen-tially the same for both start-up and regular operation excepting personnel l /) assigned to the station for training.

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12.1.2 QUALIFICATIONS O

Due to Duke participation in the operation of the Carolinas Virginia Nuclear Power Associates (CVNPA) Parr Nuclear Station in South Carolina, a number of positions at Oconee will be filled by men with extensive operating and main-tenance experience in an operating nuclear power station. Others will have many years experience in conventional stations and will be given special nuclear training. Section 12.2 gives the details of this training program and methods for qualifying station personnel. The Station Organization Chart (Figure 12-2) shows established qualifications by positions.

12.1.3 ORGANIZATION DIAGRAM A diagram showing the organization for Oconee is included as Figure 12-2. The relationship that the station organization has to the Company management is shown by Figure 12-1. For a description of the organization, see 12.1.1. The lines of responsibility for control and review of operations are discussed in 12.5.

12.2 TRAINING 12.2.1 STATION STAFF Training for operation of nuclear power stations began in 1955 for a number of the Duke General Office engineering personnel, including members of the Steam Production Department, with a special course, " Nuclear Engineering."

This course was organized and taught by Dr. Harold Lewis of Duke University. I The Steam Production Department General Office personnel have continued to keep abreast of developments in the nuclear field through industry contacts and the Duke " Nuclear Power Technical Committee." This committee, the Chairman of which is a member of the Steam Production Department, has served to disseminate information to interested engineers in the General Office relating to the design, construction and operation of the CVNEA Parr Nuclear Station. Members of the Steam Production Department staff have served on the Technical Advisory Committee for Parr most of the time since its organi-zation. This committee functions as the Engineering and Operating Management Advisory Group representing the member companies of CVNEA. Members of the General Office staff have also taken short courses, attended seminars and made visits to various nuclear power stations in the United States in order to increase their knowledge of the nuclear power field.

In 1960, the Steam Production Department furnished three engineers, each with over ten years of power plant experience, for full-time assignments in the operating supervision of Parr. In preparation for these jobs, they completed the Reactor Operation Supervisory Program at the Oak Ridge School of Reactor

' Technology in the class of 1960-61. Each obtained a Senior Operator's license for the CVTR, and have together accumulated more than twelve years of nuclear power station operating and maintenance experience in supervisory categories.

In addition, the Steam Production Department furnished an experienced Main-tenance Supervisor for Parr. After seven months of special training assign-ments at the MIR and ETR in Idaho and the Savannah River Heavy Water Pro-duction Reactors, he supervised the maintenance of the CVTR for a period of 4-1/2 years. He has now returned to Duke as an Assistant System Maintenance 304 12-2

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\ Engineer and will be available for assignment to our nuclear operations.

Four otner maintenance personnel, a chemist and a mechanical engineer have had assignments of varying lengths at Parr.

CVNPA, in addition to the Duke employees, has approximately 60 employees associated with the operation of the CVTR. Within this group are represented all of the skills associated with nuclear power station operation. It is anticipated that a substantial number of these people will be transferred to Duke, or the other member companies making up the CVNPA organization, to be available for staffing nuclear stations supplementing the skilled power plant operators from our existing stations.

The program for training the Oconee staff is designed to meet the needs of each man chosen, depending upon background, previous training and job assign-ment. The program is divided into five phases of activities: (a) Basic Funda-mental Theory; (b) Station Design; (c) Operator Training at a Comparable Nuclear Power Station; (d) On-The-Job Training and Station Oteck-Out; and (e) Operator Training Following Initial Criticality. These are described as follows:

(a) Basic Fundamental Theory All men selected for the Operator Group and certain ones in the Mainten-ance and Technical Support Groups who have not had extensive nuclear power station experience will begin their training with a basic course covering the fundamental laws of physics, nuclear theory, nuclear b instrumentation, health physics and nuclear power station theory. These courses will be taught by Duke personnel with assistance as needed by B & W and Bechtel.

(b) Station Design The Station Supervisors, all of the Operating Group and selected person-nel from the Maintenance and Technical Support Groups will participate in a station design training program organized and taught by B & W at their facil'. ties. This design instruction period of about two months includes the following:

1. Reactor Systems presents the functions, fluid conditions and descriptions of the primary and auxiliary systems. Preliminary operating procedures, safety considerations and instrumentation are an integral part of the course.

2. Nuclear Instrumentation and Control includes description of the system, detector theory, basic functions of components, station control theory and preliminary operating procedures.

3. Mechanisms includes a physical and operational description of the control rod drive assemblies, their mounting and positions. De-scription of the reactor vessel head closure and refueling equip-ment is covered.

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4. Health Physics includes instruction in measurement of radiation, O

working techniques with radioactive material and equipment, decon-tamination methods and precautions. Radiation monitoring systems are discussed.

S Chemistry presents the basic concepts of water chemistry application to the reactor system. Radiochemistry measurements, precautions, sampling and selected chemical analyses are included.

6. Reactor Protection presents both general and specific safety aspects of reactors. The history of accidents that have occurred is pre-sented. Special safety considerations of the reactor include the accident analysis and emergency procedures. Technical specifications and emergency procedures are explained. Organizational relationships and the functions of regulatory aspects are prescnted. Emphasis is placed on developing safety attitudes.

(c) Operator Training at a Comparable Nuclear Power Station Sone of the Supervisors required to obtain cold (pre-critical) Senior Operator licenses and some of the Control Operators required to obtain cold (pre-critical) Operator licenses will be selected from those already holding similar active licenses for the CVTR. If CVTR experience is not sufficiently recent, and it is deemed necessary, the men selected to obtain cold licenses will be sent to a reactor comparable to the Oconze reactors for sufficient training and operating experience to receive a ,

letter of certification to qualify them for cold license examination. )

The Supervisors and Control Operators from the Steam Production Depart-ment personnel who have had no nuclear power station experience, but will need a license prior to fuel loading, will be sent to a nuclear station comparable to Oconee for extensive operating experience.

(d) On-The-Job Training and Station Check-Out This phase of the overall training program will be at Oconee. The sta-tion staff, except for certain maintenance personnel, will be assembled at the site ten to twelve months prior to fuel loading. The on-the-job training and station check-out phases of the training program will be organized to obtain the maximum participation of the operating personnel in the on-site activities, including installation of equipment, testing and start-up. Those in training will be integrated into these activi-ties to become familiar with the station and to utilize their experience and training. Their activities will include participation in the follow-ing:

1. Testing of individual equipment and systems.

2. Developing and writing test programs.

3. Developing and writing detailed test, cperating, and refueling and emergency procedures.

4. Preparation of maintenance procedures and participation in mainten-ance work.

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B & W personnel will also participate in this phase of the training pro-gram.

1 Approximately two months before fuel loading, the personnel scheduled to obtain cold licenses for participation in fuel loading and initial opera-tion of the reactor will take license examinations. This will be pre-ceded by several weeks of on-site classroom study to review theory and to become familiar with the latest developments in the station design.

4 The examinations will conclude the formal training for this group, who will then participate in the training of the operating personnel sche-duled to obtain licenses during the first few months of operation.

(e) Operator Training Following Initial Criticality Training will be a continuing program throughout the life of the station.

However, the primary emphasis during the first few months following fuel loading and initial criticality will be training and nualifying neces-sary operating personnel for Operator licenses.

12.2.2 REPLACEMENT PERSONNEL During the normal operations of Oconee, cxtra operating and maintenance per-sonnel will be assigned to the station specifically for training purposes since it is expected that our Company will continue to consider nuclear units for the future. These men, as needed, will be drawn from the experienced O operating personnel of the Steam Production Department or employed directly into the organization at the station. The training program for replacement personnel will cover the same general material and follow the fundamental program outlined for training the original personnel, but will be presented by the station staff with outside assistance as needed. Junior engineers will be assigned to this station in regular training positions.

i 12.2.3 ON-THE-JOB TRAINING e

This section is covered by phases (d) and (e) of the training program under 12.2.1.

12.2.4 EMERGENCY DRILLS As part of the overall program of developing station procedures, an emergency plan will be developed. The plan will cover emergencies such as fire, medi-cal injury and illness, radiation and contamination accidents and other con-ditions that may result from nuclear and nonnuclear accidents. Insofar as possible, the station will be self-sufficient in handling emergency conditiot but outside agencies such as Police and Fire Departments, the AEC, etc, will be called upon as needed.

All station personnel will be thoroughly familiar with the emergency plan, and practice drills will be held as necessary for training. All outside agencies included in the plan will be informed of our procedures and their expected role in an emergency.

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12.3 WRITTEN PROCEDURES O

Written procedures will be prepared and periodically reviewed and revised as necessary to cover both normal and emergency operating conditions. These procedures will include recommended actions for all credible abnormal situa-tions. The emergency procedures will include those applicable to accidents which might conceivably result in a radioactivity release beyond the site boundary.

12.4 RECORDS Duke's standard system of record keeping with amendments and additions as necessary will be utilized at Oconee. These records will include log books, maintenance files and reports, station and switchboard log sheets and other necessary records to verify compliance with applicable governmental regula-tions.

12.5 ADMINISTRATIVE CONTROL Administrative controls will be established to assure that all operations, tests and emergencies are handled in accordance with written procedures which have been reviewed and approved by established channels. The station super-intendent has the responsibility and authority to operate the station safely within the limits of the facility license. Within these limits he has the authority to approve procedures and their subsequent revisions after review and recommendations by the station Operating and Technical Support staff. If time permits, procedures will also be reviewed and approved by the Steam Pro- j duction Department General Office prior to final approval. Any significant changes to procedures will also be subject to Steam Production Department General Office review and approval as outlined above. All changes will be reported to the General Office for record and review.

Changes in methods of operation, or any other procedures, which might adverse-ly affect nuclear safety, or might result in release of radioactive material to the environment, will first be approved by the General Office of the Steam Production Department. When appropriate, prior to such approval, other know-ledgeable departments of the Company, outside sources and/or the AEC will be consulted.

Administrative controls will also be established for making any changes to the physical station. These controls will follow the same administrative channels as outlined by the preceding paragraphs for control of procedures.

A daily review of the shif t supervisor's log and other operating data will be made by the operating engineer and/or his assistant and all nonroutine opera-tions and conditions will be reviewed by the Technical Support staff. In addition to these reviews, periodic station staff meetings will be held to keep all operating personnel advised of conditions in the station.

The Steam Production Department will make independent off-site review of all operating records, including logs, reports and special tests. The General Office staff will assume the functions generally performed by a conventional .

reactor safety committee. As is the case with all other stations on the Duke 12-6 ^-

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system, periodic visits to the station will be made by members of the General Office staff to review operations and assist vith any problems which might '

arise.

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