ML19319C265
ML19319C265 | |
Person / Time | |
---|---|
Site: | Davis Besse |
Issue date: | 08/01/1969 |
From: | TOLEDO EDISON CO. |
To: | |
References | |
NUDOCS 8002110728 | |
Download: ML19319C265 (16) | |
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D-B TABLE OF CONTENTS Section Page 12 CONDUCT OF OPERATIONS 12-1 12.1 Ih"lTODUCTION 12-1 12.2 ORGANIZATION AND RESPONSIBILITY 12-1 3 12.2.1 GENERAL 12-1 12.2.2 DAVIS-3 ESSE NUCLEAR POWER STATION ORGANIZATION 12-1 12.2. PERSONNEL QUALIFICATIONS 12-2 12 3 y c:L TPARTBIG 12-2 .
12 3 1 GENERAL 12-2 12 3 2 OPERA'IOR TRAINING PROGPAM 12-2 12 3 2.1 Nuclear Theory (Phase I) 12-3 12 3 2.2 PWR Observation (Phase II) 12-3
( 12 3 2 3 PWR Technology (Phase III) 12-3 1
12 3 2.4 PWR Operation (Phase IV) 12 h 12 3 2 5 On-The-Job Training (Phase V) 12-4 12 3 2.6 Specialist Schools and Training (Phase VI) 12-5 12 3 3 REPIACEMENT AND REFRESHER TRAH mTG 12-5 l
3 12.4 Wiumai PROCEDURE 12-6 12.4.1 EMERGENCY PIAN 12-6 l
12.4.1.1 Protective Action Levels 12-7 12.4.1.2 Station High Radiation Evacuation
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12.4.1 3 Evaluation of On-Site Conditions 12-7 1 3 l 12.4.1.4 Evaluation of Off-Site Conditions 12-T l
, 12.4.1 5 Protective Action for Local Population 12-7 Y 12.4.1.6 Hospitalization of Contaminated Casualties 12-7
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12-1 Amendment No. 3 ,
D-B TABIE OF CONTENTS (Contd) S' Section Page 3 12.4.1 7 Emergency Reserve of Personnel 12-8 12.4.1.8 Recovery Plan 12-8 12.4.2 EMERGENCY PBOCEDURE 12-8 12 5 RECORDS 12-8 12.6 ADunsrMTIVE CONTROIS 12-8 N
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LIST OF FIGURES
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(At Rear of Section) g ure No. Title 12-1 Power Grot f Organization Chart 12-2 Organization Chart 12-3 Training and Assignment Schedule f.
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D-B 12 CONDUCT OF OPERATIONS
. 3.1 IITfRODUCTION The Davis-Besse Nuclear Power Station vill be owned as tenants in c mmon by The Toledo Edison Company and The Cleveland Electric Illuminating Company.
Toledo Edison, however, will be responsible for operation of the station.
12.2 ORGANIZATION AND RESPONSIBILITI 12.2.1 GENERAL The Power Production Division of The Toledo Edison Company is responsible for the operation of all electric generating stations. The general superinten-dent of this division is located at the Acme Station and reports to the vice president, Power Group. He has direct access to the Mechanical Engineering Division on engineering matters. The station superintendents are responsible for the safe, reliable and efficient operation of the assigned station and are responsible for the routine and miscellaneous maintenance of equipment a the generating stations.
An organization chart outlining this organization is shown on Figure 12-1.
12.2.2 DAVIS-BESSE NUCIEAR POWER STATION ORGANIZATION
. . , The Davis-Besse Nuclear Power Station operating force vill consist of about
( 57 full time employees. The anticipated organization chart for the station is shown on Figure 12-2.
The normal operating shift will consist of a shift supervisor, plant control operator, reactor operator, major equipment operator, and an auxiliary equip-ment operator. The shift supervisors report to the operations engineer who is a graduate enginee.~.
The technical support group will consist of about eight people under the technical engineer. This group will function in the area of reactor physics, overall reactor and primary system performance, plant performance and instru-mentation and control maintenance.
The health physics, radiochemistry, radiological protection and conventional chemistry vill be under the responsibility of the chemical and health engi-neer with four technician level employeep under him.
Routine maintenance vill be under the responsibility of the maintenance engi-neer who will have about twelve employees under him. During maintenance outages or other times when a larger force is required, additional maintea- _
ance crews will be assigned from the Heavy Maintenance Department force or
. outside contractors. This type of maintenance vill be the responsibility of the superintendent of the Heavy Maintenance Department.
12.2 3 PERSONNEL QUALIFICATIONS
( u3: -It is anticipated that most of the personnel to man the Davis-Besse Nuclear J ( } ,
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D-B Power Station 11 come from existing positions within the Company. This q will ensure be..ing a competent group of people with extensive power station )
experience. The nuclear training and experience required of these people are being acquired at this time and vill continue to be acquired to provide a plant staff that is fully qualified for operation of a nuclear power gener-ating station.
The following plant supervisory personnel vill be graduate engineers with extensive experience in operation and maintenance of fossil-fired generating stations:
Plant Superintendent Operations Engineer Technical Engineer Results Engineer Chemical and Health Engineer Maintenance Engineer In addition, the technical engineer and at least one of the engineers under him vill have a formal nuclear education.
12 3 PERSONNEL TRAINING 12 3 1 GENERAL All engineers assigned to the Power Group cf The Toledo Edison Company have participated in the nuclear engineering courses which have been conducted by The University of Michigan and Babcock & Wilcox at the company offices and )
that are outlined in Appendix 1C. A nu=ber of the engineers in the Power Production Division have also attended special courses and others will attend these special courses in the future.
The plant superintendent for the Dav's-Besse Nuclear Power Station vill be relieved of all of his present duties in 1970 and will be assigned to the nuclear project full time. During the period from 1970 until the femal oper-ator training program commences in mid-1972, he vill receive nuclear training in selected nuclear courses, be assigned to operating plants, review desigin details and vill organize ard prepare the formal operator tra$ning program.
Additional plant supervisory people vill be relieved of all present duties in advance of the formal operator training program to assist the plant sur?rin-tendent and to obtain nuclear and specialty training. The antir'.ipated assignment dates of ther-e svoervisory people are shown on Figure 12-3 12 3 2 OPERATOR TRAINING P.OGRAM l
The purpose of the training program is to develop a complete operating staff that will assure the safe and efficient operation of the Davis-Besse Nuclear Power Station. It will also assure that a fully qualified and Atomic Energy Commission licensed staff vill be availal .c when required for initial plant operation. The plant superintendent, operations engineer, technical engineer, results engineer, one staff engineer, technical leader and all shift super-visors vill obtain their AEC senior license prior to initial fuel loading as described in 10 CFR 55 25 The plant control operators and the reactor a
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critical and low power test period and will be licensed prior to commercial operation of the plant.
A chart of tt training schedule and assign =ent times is given on Figure 12-3 A brief description of the six phases of this nuclear plant staff training program follows.
12 3 2.1 Nuclear Theory (Phase I)
This course vill cover basic nuclear physics, reactor theory, nuclear instru--
mentation, health physics and nuclear power plant fundamentals. The teaching
-staff vill include local college instructors and engineers from vendors and nuclear consultants. This course vill be presented to all personnel requiring this background before proceeding with the other phases of their training.
This course will be offered at several times during the training period to accomodate the plant personnel involved.
12 3 2.2 PWR observation (Phase II)
The plant superintendent, operations engineer, maintenance engineer, all technical staff engineers, technical leader, and all shift supervisors will receive observation experience st a nuclear power station following the theory course outlined above. This experience will consist of three months of observing the plant operation.
7 12 3 2 3 PWR Technology (Phase III) ,
This course is organized and presented by Babcock & Wilcox and will cover the design and basic functions of the components and systems furnished by this company. The course vill be presented at Babcock & Wilcox facilities follow-ing the Nuclear Plant Observation Experience and will require a period of about six weeks. This course will be attended by the plant superintendent, operations engineer, maintenance engineer, all technical staff engineers, technical leader, and all shift supervisors. In addition the plant control operators and the reactor operators will receive this course prior to report-ing for on site training. This course will cover the following areas;
- a. Reactor Physics - Review of re9.ctor physics as applied to the specific plant design.
- b. Heat Transfer and Fluid Flow - Review of the nuclear plant design, design objectives, reactor design cen%iderations and limitations.
- c. T.eactor Vessel and Internals - Review of the design, materials, fabrication, inspection, NDTT and purposes. "
- d. Pri=ary Loop Componente - Simplified two-loop heat transport
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system wi'h a description of piping, pumps, and pressurizer relative to design considerations, analyses perfomed, and
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- e. once-Through Steam Generators - Description, peculiarities, ]
heat transfer characteristics, mechanical design considera- '
tions, materials, chemistry necessities, and maintenance.
- f. Reactor Auxiliar7 Systems - Functional requirements (nomal and emergency), design objectives, criteria, and analysis including a system-by-system description, arrangements, f parameters, and equipment access and maintenance.
- g. Control Rod Drives - Description of drives and controls.
- h. Instrumentation and Control - Functional requirements and description of integrated plant control system, nuclear instrumentation and reactor protective system. Primary loop and reactor auxiliaries nonnuclear instrumentation will be covered as well as tne incore monitoring system and auto-matic data logging and on-line computer requirements.
- 1. Nomal and Emergency Power Requirements - Description of functional needs and procedures.
J. Chemistry - Water chemistry application ',o the nuclear plant, including radiochemistry measurements, sampling and chemical analysis.
- k. Health Physics - Review of radiation monitoring systems, decontamination methods and precautions and administrative procedures and controls. )
12 3 2.4 PWR operation (Phase IV)
This last course to be given off site vill be an operation training period utilizing classroom lectures, the Lynchburg Pool Reactor, and the B&W Nuclear Power Station Simulator to provide required operational experience for qual-ification to take the AEC precritical licensing examination. This training is directed toward the understanding and actual completion of operational procedures as they would be accomplished on an actual power station. This course consists of six weeks of classroom and operational training on the simulator, two weeks of training on the Lynchburg Pocl Reactor which vill include ten actual reactor startups for each trainee, and finally four weeks of shift operation on the simulator. This course will be completed by the plant superintendent, operations engineer, technical engineer, results engi-neer, one general engineer, technical leader and all shift supervisors.
12 3 2 5 on-The-Job Training (Phase V)
It.is anticipated that all Davis-Besse personnel vill have completed their off site training and be ready for plant assignment with the initiation of the plant startup activities. This phase of the training program vill be organized to obtain the maximum participation of the plant staff. They will participate in:
- a. Preparing test programs and test procedures. ; 0357 j 1
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4 D-B gm b. Testing of components and systems.
- c. Preparing operating, refueling and emergency procedures.
- d. Evaluating routine and emergency operating procedures.
- e. Preparing maintenance procedures.
- f. Evaluating maintenance procedures and observing the installation of major and auxiliary systems and equipment.
- g. Preparation of the AEC operating license material with particular e=phasis on the operational aspect of the technical specifications.
- h. Calibration of all instruments and control systems.
A few months prior to fuel loading, the personnel scheduled to obtain an -
operator's license for participation in fuel loading and initial operation of the reactor, will take license examinations. This will be preceded by several weeks of on-site classroom study to review the theory covered in earlier cour.1es and to familiarize the staff with the latest developments in the station design. The procurement of the AEC Senior Operating License by this group will complete their formal initial training. The plant con-trol operators and reactor operators will attend similar classes, receive actual experience on the Davis-Besse plant during the startup test program, and be pn 3ented to the AEC for licensing prior to commercial operation.
12 3 2.6 specialist schools and Training (phase VI)
Engineers, technicians, and the maintenance engineer will be involved in specialized courses to prepare them for their assigned task. These courses are from two weeks to several months in duration and will provide both theoretical and practical training. The vendors will provide some of these courses, while others will be obtained at colleges and government facilities.
The types of courses included in this group are nuclear engineering, fuel management, instrumentation, radiation protection, radiochemistry and-main-tenance of major equipment.
12 3 3 REPIACEMENT AND mmaat TRAINING To provide the necessary replacements for the initial group of plant personnel who will leave through retirement, prcmotion, etc., additional employees will be added to the station staff as necessary. These personnel vill receive similar training to that outlined for the original personnel. This training will be conducted by the station staff with outside assiste.nce as required.
All of Phase II training for these replacement personnel vill be obtained
- using our operating reactor.
Refresher training for all station pr rsonnel will be given on a. continuing
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basis. This will cover nuclear theory, reactor physics, health physics, systems design and operation, instrumentation and control and operating pro-
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l 12.4 Muma PROCEDURB Written procedures for normal and emergency operating conditions will be prepared. These procedures vill be reviewed periodically and revised as necessary. The procedures will incluie a course of action for the operator l for all credible off-standard conditions. Included vill be emergency pro-l cedures applicable to accidents which might release radioactivity beyond the site boundary..
12.4.1 DERGENCY PIAN As a part of the program of developing station procedures, an emergency plan will be developed prior to operation. This plan vill cover emergencies such as fire, medical injury and illness, radiation and contamination accidents, ;
and other emergency conditions that may result from operational malfunctions, l l natural disasters, and civil disturbances. Insofar as possible, the station t
will be self-sufficient in handling emergency conditions, but outside agencies such as the U. S. Coast Guard, Ohio State Highway Patrol, State of.
l Ohio Department of Health, Ottawa County Civil Defense, local police and fire departments, the AEC, and area hospitals. and medical clinics, vill be called upon as needed. These agencies vill be familiarized with the Davis-Besse -
Nuclear Power Station, with the emergency plan, and with their expected role l , 3 in assisting with an emergency situation. The se wices of professional con-sultants in the areas of medical radiation and radiation accident control will be obtained if deemed necessary. Alerting procedures will be included in the emergency plan in order to quickly bring these outside forces into I- active assistance if required.
All station personnel vill receive copies of the emergency plan prior to plant operation, and will be required to be thoroughly familiar with the emergency plan; practice drills vill be held on a regular schedule for tzsining.. Periodic review of their expected role in an emergency situation vill be conducted with all outside agencies, and communications will be routinely tested.
Procedures vill be provided to maintain the emergency plan up to date and responsive to personnel and organization changes in participating organi-zations ani agencies.
Among the bases ~ for the emergency plan will be 10 CFR 20,10 CFR 100, v
r-0359 Amendment,No. 3l 12 g ,
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D-B Federal Radiation Council Report No. 5, and Section 2 (Site and Environment) of this PSAR.
12.4.1.1 Protective Action Levels Initiation of designated alarms vill alert the Ccatrol Room to the possible existence of an accident in which the release of radioactive material could occur to the environment.
After receiving one or more of the designated alarms, the Operator vill evaluate the conditions producing the alams, and if instrumentation indi-cates that radiation has resulted which presents a danger to station personnel or the. surrounding population, he vill sound the radiation emergency plan alam. The audible signal vill be unique and distinguishable and vill sound throughout the station and surrounding site area.
12.4.1.2 Station High Radiation Evacuation Upon the sounding of the station radiation e=ergency pJan alam, all station personnel and visitors except those assigned to the Control Room vill report to an emergency control center. All evacuees will be surveyed b*, an emer-gency monitor prior to leaving the station boundary. All personnel remaining at the station to perform emergency opersting procedures vill be surveyed for possible contamination. Accountability of site personnel vill be pro-vided for.
( 12.4.1 3 Evaluation of on-Site Conditions 3 To evaluate the radiation levels on-site, readings will be taken from the station radiation monitoring system in the Control Room, and a monitoring team vill survey the station and i=ediate environment. Appropriate records vill be kept of the results of the surveys.
12.4.1.4 Evaluation of Orf-Site Conditions To evaluate the radiation levels off-site, a monitoring team vill survey designated areas reflecting accident and post-accident vind conditions.
Appropriate records will be maintained.
12.4.1 5 Protective Action for Local Population If radiation monitoring teams have mI~rt:d high radiation levels on the off-site survey and these radiation levels ale above the average projected dose limit recommended by the Federal Radiation Council, and radiation levels are increasing, appropriate local, state and federal authorities vill be notified.
These authorities vill be informed that a major release of radioactive material occurred at the Davis-Besse Station; evacuation of the low popula-
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tion zone may then be perfomed by prearranged methods.
12.4.1.6 Hospitalization of Contaminated Casualties In the event a medical injury occurs that necessitates hospitalization before decontamination, action vill be taken for a preliminar'/ survey of the
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the emergency plan may be initiated.
12.4.1 7 Emergency Reserve of Personnel The einergency plan vill make provisions for the obtaining of additional personnel from within the Co=pany, from other nuclear power stations, out-side agencies, and appropriate vendors if required in the event of an emergency.
3 12.k.1.8 Recovery Plan Part of the emergency plan vill pertain to the requirements of a plan to return the station site and environment to an acceptable standard of rradia-tion safety.
12.4.2 EMERGENCY PROCEDUEE Emergency procedures vill be prepared, distributed, initiated, and main-tained current to implement the Davis-Besse Nuclear Power Station emergency plan.
12 5 RECORDS Toledo Edison's regular system of record keeping, revised as necessary, will
_j be utili::ed at the Davis-Besse Station. These records vill include peman-1l ent logbooks, daily log sheets, recorder sheets, maintenance files and other special records which verify compliance with various governmental regula-tions.
12.6 AIIENISTRATIVE CONTBOIS l Administrative controls will be established to assure that all operations, j maintenance, tests and emergencies vill be handled in accordance with the
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vritten procedures which have been reviewed and approved by established authorities. The station superintendent has the responsibility and authority 3 l to operate the station within the limits of the administrative controls.
3 l A Station Review Board consisting of the station superintendent and the eupervisors of the operations, technical, health physics and maintenance
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, groups vill be permanently created to meet periodically and reviev nomal operations and written procedures to assure safe and continuous operation.
. This Board vill also review every abnormal occurrence or departure from the
. . technical specifications to determine its cause and vill make recommendations
" to the General Superintendent, Power Production Division prior to any changes being made.
A Company Nuclear Review Board vill also be established, consisting of Company engineers and outside consultants as required to audit and reviev 3 l station operations and activities of the Station Review Board. This Board vill review any major abnomal occurrence or departure from technical speci-fications and review any matter referred to it by the Station Review Board.
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It is anticipated the Vice President, Power Group; Chief Mechanical Engineer; General Superintendent, Power Production; Davis-Besse Station Superintendent;l 3 Station Electrical Engineer; and Nuclear Engineer in the Mechanical Engineer-ing Division vill be members of this Board.
A daily review of operating logs, charts and other data vill be made by engi-neers and technicians under the technical engineer to assure that the station l 3 is being operated in a safe and efficient manner.
Periodic staff meetings will be held to keep all operating personnel advised of current conditions in the station. l3 e
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NUCLEAR TEORY(TOLEDO)
PWR OBSERYATION (OPERATING PLANT)
PWR TECHNOLOGY (LYNCMURG)
PWR OPERATION (LYNCHBURG)
ON-THE-JOB TRAINING S TESTING (DAVIS-BESSE STATION)
! UCENSE REVIEW AND EXAMINATION (DAVIS-BESSE STATION)
ASSIGNMENT DATE TO STATION STAFF I I SPECIALTY SCHOOLS AND TRAINING
$ THESE PERSONNEL ASSIGNED TO STAFF APROXIMATELY OCTOBER 19T2 AT WHICH TIME PHASE I WILL BE REPEATED FOR THEM. l l .
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)ME ME MMM MMMMMMMEMMMM IMMM MMM MB MME MMMMMMEMMMM IMEM MMM MB MME MMMMMMMEMNIME IMMM i MMMMMMMIMMM IMMM MIEW MB i MMMMMEMMMM IMMM MBEM BIE BEINE MIMEBIEIEEEllIMEMME!!M IMEM MB MEMMMMMEMMMM IRIMM llEIE MIERIIMBEMIIEEMMMM IMMER MMMMMMMMMMMM IMMBE MMMMMMMERIEMBEM IMMM MMM ME MBE i MMMMMMMM IMMM i MMMMMMMM IMMM i MMMMMMMM IMMM i MMMMMMMM IMMM i M6MMEmmm JL I II III IV V A JL JL JL JL JL JL BEGIN FUEL LOADING COMMERCIAL OPERATION DAVIS-BESSE NUCLEAR POWER STATION TRAINING AND ASSIGNMENT SCHEDULE Figure 12-3 i
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