ML19329D994
| ML19329D994 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/31/1967 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8004090519 | |
| Download: ML19329D994 (23) | |
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TABLE OF CONTENTS 12.
CONDUCT OF OPERATIONS Section Page
12.1 INTRODUCTION
12.1-1 12.2 ORGANIZATION'AND RESPONSIBILITY 12.2-1 12.3 PERSONNEL TRAINING 12.3-1 12.3.1 TRAINING INITIAL PLANT STAFF 12.3-1
- 12. 3. 1. 1 Basic Reactor Physics and Eneineerine Course (Phase I) 12.3-2
- 12. 3. 1.2 Operating Experience at a Nuclear Plant (Phase II) 12.3-2
- 12. 3. 1.3 Nuclear Steam Supply System Design Lectures (Phase III)
- 12. 3-2 12.3.1.4 Nuclear Plant Operational 1 raining (Phase IV) 12.3-3 12.3.1.5 Start-up Activities (Phase V) 12.3-3 12.3.1.6 Soecialist Schools and Trainine (Phase IV) 12.3-4 12.3.2 REPLACEMENT AND REFRESHER TRAINING 12.3-4 12.3.3 EMERGENCY DRILLS 12.3-5 12.4 WRITTEN PROCEDURE 12.4-1
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12.5 RECORD 12.5-1 12.6 ADMINISTRATIVE CONTROLS 12.6-1 12.7 INDEPENDENT AUDIT OF PLANT OPERATIONS 12.7-1 LIST OF FIGURES Figure Number Title 12.2-1 Operating Organization - Rancho Seco No. 1 12.3-1 Plant Staffing and Training Program t
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Amendment'3 12-1
12.
CONDUCT OF OPERATIONS 12.1 ISTRODUCTION The purpose of this section is to provide a general description of the manner in which SMUD plans to operate and maintain the plant. The pro-grams and techniques presented have been used successfully at a number of existing, operating, nuclear power plants and have been amplified or adapted, where necessary, to meet the District's particular needs.
Special l
emphasis is placed on personnel training and administrative control to
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assure that a qualified staff is assigned to the plant and strict adherence I
to all plant safety regulations is maintained.
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12.2 ORGANIZATION AND RESPONSIBILITY The organization for operations of the plant is shown in Figure 12.2-1.
l1 The plant organization has been divided into five areas of responsibility --
analyst, technical, operations, maintenance, and administrative support.
The area supervisors and analyst will report to the plant superintendent and his assistant (s). The plant superintendent will be responsible for all site activities. The plant superintendent will report to the Operations Department manager who is responsible to the general manager for the operation and maintenance of generation, transmission, and distribution facilities. All plant personnel will be carefully selected and trained for their assigned duties with particular emphasis focused upon the super-visory, technical, and operating staffs to assure safe and efficient operation of the plant.
Figure 1.6-2 shows the relationship of the plant staff to the total District organization and the safety review and audit committees established for this plant.
It is SMUD's intent to assign engineering personnel who are graduate engi-neers with appropriate experience and specialized training in their areas of responsibility. Wherever possible these positions will be filled by personnel with operating experience in their respective fields.
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training program, however, has been developed to prepare an applicant with a minimum background in the field. The technical staff, engineers and technicians, will be provided with a sufficiently broad training to assure backup in all critical areas of responsibility. As an example, the mechan-
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ical engineer will have sufficient training to back up the nuclear engineer in specific areas.
Selected engineers will also be licensed as AEC secior 1
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operators prior to initial fuel loading.
The Technical Supervisor is responsible for the engineering and technical work to assure proper functioning of the Nuclear Power Plant; for staffing, training, and performance of assigned technical personnel; for providing technical data for the Technical Specifications and in-house standards and procedures; for preparation of technical criteria for any required design changes; and is responsible for developing radiation protection standards and procedures.
The Operation Supervisor has functional responsibility for the operation of the nuclear plant; for participation in the planning and scheduling of work; for directing the safe and efficient use, occupancy, and upkeep of the nuclear power plant and related facilities.
2 The Analyst will prepare license applications and amendments; will audit the operations for the safety of operation and licensing compliance; will represent the District in relationships with the Compliance Division USAEC; will prepare routine reports as required by the operating license; and will be a member of and assigned secretary for the Nuclear Operations Safety Review Committee.
The normal operating shift will consist of one shift supervisor, one senior control operator, one control operator, one auxiliary operator, and one equipment attendant. The shift supervisors will be responsible to the operations supervisor for the safe and efficient operation of the plant Amendment 2 12.2-1
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during their assigned shift. The operation supervisor and shift super-visors will all be licensed as AEC senior operators prior to initial fuel loading.
The senior control operators and control operators will be 2
presented to the AEC for licensing prior to commercial operation of the plant.
1 The maintenance force will consist of 13 men qualified to perform the electrical and mechanical maintenance of nuclear plant systems.
This group, with assistance from the Hydroelectric Division, will perform all routine plant maintenance except major turbine-generator overhauls and reactor refueling.
Initially, these functions - turbine-generator over-hauls and reactor refueling - will be performed by outside crews, working under the direction of the District. At some future date the addition of nuclear power plants and increased personnel may justify performing of these tasks by SMUD crews. The maintenance activities will be directed by the maintenance supervisor who will report directly to the plant super-intendent and his assistant.
The many special requirements of a nuclear power plant will justify the establishment of an administrative staff for this plant.
These tasks include clerical and record-keeping, plant security and accommodating visitors.
The administrative assistant in charge of this group will be responsible to the plant superintendent.
SMUD will have prime responsibility for the start-up program.
The plant start-up organization will include all of tht normal plant staff, except some of the administrative staff, plus a number of vendor and architect /
cngineer personnel to provide adequate coverage in all areas.
1 SMUD is currently developing a nuclear engineering group for technical 2
support of the plant staff (see Appendix 1C).
Use also will be made of the consulting services of Babcock & Wilcox, and one or more engineering firms as required. The District currently has an engineering-consultant contract with NUS Corporation and with the Bechtel Corporation.
Plant safety will be the responsibility of the plant superintendent.
He will be assisted in this task by the area supervisors, analyst, and the 2
radiation protection engineer.
The radiation protection engineer is a member of the plant Technical Support Group and will have direct line of communication to the plant superintendent.
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PLAT SUPERINTENDEt (1
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OPERAT MAINTENANCE ANALYST SUPERVIS SUPE SOR (CE,SL)
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MECHANIC-WELDER (4)
SENIOR CONTROL HELPER (2)
OPERATOR (L)
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ELECTRICAL CONTROL SUB-FORMAN OPERATOR (L)
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RE0VIREMEtiTS C COLLEGE GRADUATE hTt T
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SL AEC SENIOR OPERATORS LICENSE (includes precritical examination)
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FIGURE 12.2-1 OPERATING ODRGA';IZATIO:;
RANCHO SECCO :;O. 1 esuucz bb' TOTAL PLANT STAFF = 65 SACRAMENTO MU?)NICIPAL UTluTY DISTRICT A=endment 2 A
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<12.3 PERSONNEL TRAINING-(
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' TRAINING INITIAL PLANT STAFF e
- The training of District personnel began in 1966 when a number of the engineering and management personnel from SMUD's operating and engineering departments enrolled in reactor engineering courses at Sacramento State 1
College Selected personnel have also attended manufacturer-sponsored seminars and one employee attended a nuclear engineering short course at the University of Michigan. The District has also employed a plant super-intendent with a M.S. in Nuclear Engineering and ten years of operating l2 and engineering experience in the nuclear field.
The District plans to recruit three additional members of the plant operating staff in-1968. Figure 12.3-1 is a bar chart which illustrates the District 's current plans for recruiting, staffing, and training. This chart is only a 2
guide since timing for personnel recruitment and training will largely depend upon the experience and background of those personnel recruited.
The training program of the plant staff will be under constant review by the District and the presently assigned plant superintendent.
The training program has been designed to meet the requirements of the personnel selected for each_ position. The training period will exceed four years for some of the key personnel and be'only a few months for some of the administrative staff. All off-site training'will be completed prior to the start-up period to enable the District personnel to participate in the plant start-up and all' ensuing activities.
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The training program' includes the following areas:
Phase I.
Basic reactor physics and engineering course 1
Phase II.
Observation of the operation of a nuclear plant A
Phase III.
Nuclear steam supply system design lectures by Babcock and Wilcox 3
Phase IV.
Nuclear Plant Operation Training on the D&W simulator Phase V.
Start-up activities t
Phase VI.'
. Specialist schools and training The primary purpose of the training program is to develop an; operating staff that will assure the safe and efficient operation of our nuclear power plant.
This. program will also assure us of adequate AEC licensed personnel when 4
they are required. The plant superintendent, assistant plant superintendent, operations supervisor, nuclear engineer, mechanical engineer and all the shif t supervisors will obtain their AEC. senior license prior to initial
' fuel loading as described in 10 CFR 55.25.
The senior control operators and control operators will obtain their-operating' experience at the plant during the -precritical 'and low power test period and will be licensed prior.
to commercial operation of.the plant.
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A brief description of the six phases of.this nuclear plant staff training program follows.
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Personnel Training 12.3.1. 1 Basic Reactor Physics and Encineerine Course (Phase IT This course will cover basic nuclear physics, reactor theory, nuclear instrumentation, health physics and nuclear power plant fundamentals. The teaching staff will include local college instructors and engineers from vendors and nuclear consultants. This course will 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 1
the training period to accommodate the plant personnel involved.
- 12. 3. 1.2 Operating Experience at a Nuclear Plant (Phase II)
The plant superintendent, assistant plant superintendent, operations supervisor, maintenance supervisor, all technical staff engineers, and all shift supervisors will receive observation experience at a nuclear power station following the theory course outlined above.
This experience will y
consist of five months of obset ving the plant operation.
- 12. 3. 1. 3 Nuclear Steam Supply System Design Lectures (Phase III)
This course is organized and presented by Babcock and Wilcox and will cover the design and basic functions of the components and systems furnished by this company.
The course will be presented at Babcock and Wilcox facilities following the.uclear Plant Observation Experience and will require a period of about six weeks. This course will be attended by the plant super-intendent, assista-plant superintendent, operations supervisor, mainte-nance rrrrervisor, technical staff engineers, and all shift supervisor s.
In addttion the sermor control operators and the control operators will reccive this course prior to reporting for on site training.
This course will cover the f ollowir g areas:
a.
Reactor Phyuics - Review of reactor physics as applied to the 1
specific plant design.
b.
Heat Transfer and Fluid Flow - Review of the nuclear plant de-sign, design objectives, reactor design considerations and limitations.
c.
Reactor Vessel and Internals - Review of the design, materials, fabrication, inspection, NDTT and purposes.
d.
Primary Loop Components - Simplified two-loop heat transport sys-tem with a description of piping, pumps, and pressurizer relative to design considerations, analysee performed, and materials.
e.
Once-Through Steam Generators - Description, peculiarities, heat transfer characteristics, mechanical design considerations, materials, chemistry necessities, and maintenance.
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- 12. 3-2 Amendment 2
Personnel Training (V'l f.
Reactor Auxiliary Systems - Functional requirements (normal and-emergency), design objectives, criteria, and analysis in-cluding a system-by-system description, arrangements, para-meters, and equipment access and maintenance.
- g. - Control Rod Drives - Description of drives and controls.
h.
Instrumentation and Control - Functional requirements and des-cription of integrated plant control system, nuclear instru-mentation and reactor protective system.
Primary loop and reactor auxiliaries nonnuclear instrumentation will be covered as well as the incore monitoring system and automatic data logging and on-line computer requirements.
- i. Normal and Emergency Power Requirements - Description of functional needs and procedures.
J.
Chemistry - Water chemistry application to the nuclear plant, in-cluding radiochemistry measurements, sampling and chemical analysis.
k.
Health Physics - Review of radiation monitoring systems, decon-tamination methods and precautions and administrative pro-cedures and controls.
I 12.3.1.4 Nuclear Plant Operational Training (Phase IV)
This last course to be given off site will be an operation training period utilizing classroom lectures, the Lynchburg Pool Reactor, and the B&W Nu-clear Power Station Simulator to provide required operational experience for qualification 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 4
station. This course consists of six weeks of classroom and operational i
training on the simulator, two weeks of training on the Lynchburg Pool Reactor which will include ten actual reactor startups for each trainee, and finally four weeks of shif t operation on the simulator.
This course will be completed by the plant superintendent, assistant plant superin-tendent, operations supervisor, nuclear engineer, mechanical engineer, and all shift supervisors.
12.3.1.5 Start-up Activities (Phase V)
It is anticipated that all SMUD personnel will have completed their off-site training and be ready for plant assignment with the initiation of the plant start-up activities. This phase of the training program will be organized to obtain the maximum participation of the plant staff.
They will partici-
_pate in:
a.
Preparing test programs and test procedures.
Tb.
Testing of components and systems.
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Preparing operating, refueling and cmergency 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 cquipment.
g.
Preparation of the AEC oparating license material with particular emphasis on the operational aspect of the technical specifi-cations.
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 1
of the reactor, will take license examinations. This will be preceded by several weeks of on-site classroom study to revicu the theory covered in earlier courses and to familiarize the sa ff 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 senior control operators and control operators will attend similar classes, re-ceive actual experience on the Rancho Seco plant during the startup test program, and be presented to the AEC for licensing prior to commercial operation.
- 12. 3. 1.6 Specialist Schools and Training (Phase VI)
Engineers, technicians, and the maintenance supervisor will be involved in one or more 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 gov-crnment facilities. The types of courses included in this group are nuclear engineering, fuel management, instrumentation, radiation protection, radio-chemistry and maintenance of major equipment.
12.3.2 REPLACEMENT AND REFRESHER TRAINING The training of replacement personnel and re-training of the initial staff will be a continuing program.
All plant personnel will be periodically enrolled in refresher courses or courses covering new concepts to assure the continued safe and efficient operation of the plant.
These will be both on-site and off-site and will vary from short lectures on health-physics to graduate courses en nuclear physics. The training cf replace-ment personnel in the crafts and technical areas will be handled by the District's apprentice program.
This program includes both practical and theoretical training and requires a minimum of three years to produce a journeyman.
There will also be cross training between the two technician fields to assure better coverage.
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- 12. 3-4 Amendment 1
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Replacement personnel for the operating group will normally be obtained by s_,
promotion. A continual, on-site operator training program will be estab-lished to assure the availability of qualified personnel.
Personnel in each job classification will be encouraged to train for the next position and obtain the required AEC Operator's License, where applicable.
Well-qualified senior control operators will be eligible for promotion to shift supervisor.
In preparation for this promotion, they will be given addi-tional courses on the plant systems and will obtain their AEC Senior Operators License.
The replacement training for the engineers in the Technical Support Group will be based on two training programs.
First, all engineers in the initial staf f will be trained in an adequate number of fields to provide engineering back-up in all critical areas of responsibility.
Second, one or more engi-neers will be provided on-site and of f-site training to prepare them for several of the staff positions.
The replacement and refresher training program will be administered by the administrative assistant. The Technical Support Group will keep the pro-gram current and provide instructors for all on-site courses. The plant superintendent will have over-all responsibility for the program.
12,3.3 EMERGENCY DRILLS All station personnel will be thoroughly familiar with the site emergency plan and practice drills will be held on a routine basis to evaluate the efficiency of the staff.
All outside agencies included in the plan will be informed of the procedures and of their expected role in an emergency.
Training sessions will be provided for outside personnel, when required, to assure their understanding of the procedures and the hazards involved.
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OPE ft ATlONS SUPEftVISOR (AEC St NIOR OPE RATORS LICENSE) 5 E=Y='OOk MECHANICAL E NGINEER (T HE ftM A L)
NUCLE Aft ENGINEER (AEC SENIOR OPERATORS LICE NSE)
INSTFtUMENT AND CONTROLS ENGINEER MECHANICAL ENGINEE11 (AEC SENIOR OPERATING LICENSE)
CHEMICAL AND RADIATION ENGINEER FtAOlATION TECHNICIANS (4)
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b INSTitUME NT AND CONTROLS TECHNICIANS (3)
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SHlf T SUPERVISOR (5)
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AUXILIARY OPERATOR (5) 4 EQUlPMENT ATTENDANT MAINTENANCE SUPERVISOR MECHANICAL FOREMAN (2)
ELECTitlCAL TOREMAN (1)
ELECTRICAL AND MECHANICAL CREWS (9)
ADMINISTRATIVE AlD 5
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l 12.4 WRITTEN PROCEDURE Detailed written procedures for all normal operations and abnormal and emergency conditions will be. prepared and evaluated prior to initial fu'el i
loading. These procedures will include a site emergency plan which pro-vides the necessary pre-arrangement and organization of plant personnel to deal ef fectively with any foreseeable emergency at the plant site.
These would include fire, medical injury or illness, radiation ind contamination l
accidents and other conditions that may result from nuclear or non-nuclear accidents. The site emergency plan will be coordinated with the State of
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California and local disaster organizations. The plant will be equipped i
to handle all emergency conditions; however, outside agencies such as police and fire departments, State of California, local disaster organiza-l tions, the AEC, and others will be called upon if they can provide assist-ance during an emergency condition.
t All procedures will be periodically reviewed, and revised, as necessary, to cover changing conditions or modified standards.
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! O 12.5 RECORD Records documenting the operation and maintenance of the plant, in accord-ance with District policies and AEC requirements, will be maintained.
The routine operating records will include log sheets, log books, analog record-ings and digital records on all significant plant parameters.
.taintenance records will include inspection, calibration and maintenance history on all j
significant components.and systems.
Detailed records of the operational l
testing of nuclear safeguard systems and components, plant malfunctions, i
and other significant events will be maintained.
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\\M 12.6 ADMINISTRATIVE CONTROLS Administrative controls will be established to assure that all operations, tests, and emergencies are handled in accordance with written procedures which have been written and approved by established channels. All proposed design modifications, proposed changes in operating and emergency procedures and proposed tests will be subject to an established review procedure. Two levels of review will be required on actions affecting plant safety.
A review committee composed of operating and technical personnel from the plant staff will provide the first review. The second level of review will be performed by the Nuclear Operations Safety Review Committee composed primarily of persons from Nuclear. Design and Construction. Tests or changes that do not affece plant safety will require approval of the Nuclear staff from the office of the assistant chief engineer, engineer.
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12.7 INDEPENDENT AUDIT OF PLANT OPERATIONS In addition to the "in house" controls mentioned in 12.6, an independent l
audit of plant operation with particular emphasis on aafety, will be con-l ducted as required This audit will be madd by outside consultants not j
otherwise directly involved in the nuclear operation.
They will make periodic unannounced visits to the plant, examine logs, interview person-4 nel, and otherwise observe operations. Their findings will be reported directly to SMUD's general manager and chief engineer, i
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