ML20137Y847
| ML20137Y847 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/28/1981 |
| From: | INSTITUTE OF NUCLEAR POWER OPERATIONS |
| To: | |
| Shared Package | |
| ML20137Y834 | List: |
| References | |
| GPG-01, GPG-01-R01, GPG-1, GPG-1-R1, NUDOCS 8603120405 | |
| Download: ML20137Y847 (21) | |
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- ATTACHMENT B 7 -
NUCLEAR POWER PLANT SHIFT TECHNICAL ADVISOR i
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RECOMMENDATIONS FOR POSITION DESCRIPTION, QUALIFICATIONS, EDUCATION AND TRAINING
-j THE INSTITUTE OF NUCLEAR POWER OPERATIONS I
$ & S __- __
OFFICIAL RELEASE 9603120405 860228 PDR ADOCK 05000461 PDR p
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Document Number April 28, 1981 GPG -01 is pesantted. No ot3er reproduction.
Deproduction Dy sences ettlittee for katoreal coscany useis ;ermatted.
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1 I FOREWORD .
. d In developing recommendations for the STA position and .giving -+
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- consideration to the current shortage of qualified engineering ,.
graduates to fill the interim. positions, the working groups -
l assisting in developing the guidelines . attempted to identify those ' areas of education and levels of experience considered jg necessary to effectively accomplish the position's most important y func' tion -
accident assessment. Recognizing that many h 1' engineering or scientific degree programs do not normally include the range and depth of technical subjects required for accident j!
assessment, the recommendations included herein identify the j [
subject areas and depth of study necessary 'but do not specify y
- through what programs they should be acquired.
j The user is cautioned to ensure that the recommended education and training is conducted in a professional manner by competent instructors and at the proper level. Institutions and programs accredited by recognized agencies such as ECPD/ ABET and INPO l ensure that adequate sta'ndards are. met.
The program identified should provide the technical depth i necessary to meet long-term qualification requirements of both the Senior Reactor Operator and the Shift Supervisor.if the STA Al position . is eliminated. Since the shift supervisor position ,
normally is involved in a broader range of managerial ~ responsi-bilities, additional training and . education in non-technical -
subjects such as technical writing, oral communication and f ,
decision making is recommended. i l
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TABLE OF CONTENTS SECTION PAGE
- 1. Introduction....................... .................... 1 ,
- 2. Definitions............................................. 3
- 3. Goal ................................................... 6
- 4. Position Description.................................... 7
- 5. General Education and Experience........................ 10 5 . 'l Education and Training............................. 10 5.2 Experience......................................... 10 5.3 Absences from STA Duties........................... 10
- 6. Education and-Training Requirements..................... 11 6.1 Education.......................................... 11 6.1.1 Prerequisites Beyond High School Diploma..................................... 11 6.1.2 College Level Fundamental Education.................................... 12 6.2 Applied Fundmentals - Plant Specific................. 13 6.3 Management / Supervisory Skills....................... 14 l
6.4 Plant Systems....................................... 14.
6.5 Administrative controls............................. 15 6.6 General Operating Procedures......................... 15 6.7 Transient / Accident Analysis and Emergency Procedures............................... 16 6.8 Simulator Training................................... 16 6.9 Annual Requalif,1 cation Training...................... 18 11 Revision 1
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- 1. INTRODUCTION After the accident at Three Mile Island, investigations by several committees and the Nuclear Regulatory Commission concluded that certain deficiencies may exist in the level of technical expertise generally available to the shift opera-ting staff prior to, during, and immediately after an accident or severe plant transient. Although adequate expertise may be available some time later, the lack of ,
skilled analytical capability during such occurrences may contribute to equipment damage or danger to the plant staff and the public. Subsequent recommendations and regulations require that additional technical expertise be made available to each operating shift. Current regulatory requirements identify those individuals providing this expertise on shift as Shift Technical Advisors (STAS).
The purpose of this document is to describe the position and identify specific areas of formal education, plant-specific training and experience necessary to assure an advanced level of analytical ability on shift. These recommendations will provide a level of technical ability that is essential to improved operational safety and are consistent with regu-latory requirements. This position was developed in conjunc-l tion with representatives of utilities, equipment vendors and engineering educators, giving consideration to specific con-tributions the function must make to shift operations.
For convenience, the necessary contributions are identified in the form of a position description. Although this format suggests that the function will be performed by a new posi-tion, it is not intended to preempt management's prerogative to accomplish the function through other qualified indivi-duals within an existing organizational structure, f
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It should be noted that the areas of formal education identi-fled are not normally included in any one course or in the courses for any one established engineering or related sci-entific degree program. Rather, the areas and depths . of study are those needed to perform the function effectively.
The areas identified do provide a basis for either exempting certain subject areas for qualified engineering graduates or for establishing developmental programs for non-graduates or graduates of a degree program that does not include the requisite subject areas, i
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- 2. DEFINITIONS The definitions given below are of a restricted nature for the purpose of these recommendations.
Contact Hour of Instruction - A one-hour period in which the course instructor is present or readily available for 5 fj instructing or assisting students: lectures, seminars, discussions, supervised study, problem-solving sessions, quizzes, and examinations are considered contact periods under this definition.
Education -
Successfully completed college-level work which may or may not lead to a recognized degree in a discipline related to the position.
! Experience -
Applicable work in design, construction, pre-operational and startup testing activities,- operation,
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i maintenance, or technical services. Observation of others performing work in the above areas is not experience. l Licensed Operator -
Any individual who possesses an oper-i ator 's license pursuant - to Title 10, Code of Federal Regula-tions, Part 55, " Operators' Licenses".
Licensed Senior Operator -
Any individual who possesses a senior operator's license pursuant to 10 CFR Part 55.
Manacer of Nuclear Power -
The individual in the utility organization who is directly responsible for the operation of that utility's nuclear power plants, usually the person to whom the Plant Manager reports.
Nuclear Power Plant -
Any plant using a nuclear reactor to produce electric power, process steam or space heating.
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Nuclear Power Plant Experience -
Experience acquired in the preoperational and startup testing activities or operation of nuclear power plants. Experience in design, construction, and operational training may be considered applicable nuclear power plant experience and should be evaluated on a case-by-case basis.
Experience acquired at military, non-stationary, propul-sion, or production nuclear plants may qualify as equiva-lent to nuclear power plant experience on a one-for-two time basis up to a maximum of three years.
Training may qualify as equivalent to nuclear power plant experience if acquired in reactor simulator training programs to a maximum of three (3) month's credit.
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On-the-job training may qualify as equivalent to nuclear I power plant experience on a one-for-one time-basis for up to a maximum of two year's credit.
Nuclear Reactor - Any assembly of fissionable material which is designed to achieve a controlled, self-sustaining neutron chain reaction.
On-The-Job Training -
Participation in nuclear power plant start up, operation, maintenance, or technical services as a trainee under the direction of experienced personnel.
i Related Technical Training -
Formal training beyond the high
. school level in technical subjects associated with the posi-tion in question, such as acquired in training schools or programs conducted by the military, industry, utilities, universities, vocational schools, or others. Such training programs are of a scheduled and planned length and include text material and lectures.
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STA -
Shift Technical Advisor - The individual at a nuclear power plant assigned to evalaate plant conditions and provide advice to the Shift Supervisor during plant transients, acci-l dents and on matters related to operational safety. ;
Utility (owner Organization) -
The -organization, including '
the on-site operating organization, which has overall legal, * '
financial and technical responsibility for the operation of one or more nuclear power plants. This includes contracted ;
t personnel. ;
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- 3. GOAL The goal of creating the STA position is to improve the qual-ity of plant technical management and operation by providing
. additional on-shift expertise in the area of operational safety, thus reducing the probabilty of abnormal or emergency condition occurrences and mitigating the . consequences of these conditions if they do occur.
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- 4. POSITION DESCRIPTION The responsibilities-of the Shift Technical Advisor should be documented in such a way that the incumbent clearly under-stands the duties and responsibilities of the position. The following position description is a suitable method for des-cribing the work to be performed and the measures of incum-bent peformance. "
Function When the plant is not in the cold shutdown condition:
Maintain independence from normal plant operations as necessary to make objective evaluations concerning plant safety.
Provide advanced technical assistance to the operating shift complement during normal and abnormal operating conditions.
General Qualifications That combination of education, . training and nuclear plant experience identified in Sections 5 and 6.
- An in-depth understanding of nuclear plant equipment, systems and operating practices and procedures.
I General Duties During assigned tour of duty be cognizant of plant and equipment status.
- Make objective evaluations of plant operations and l advise or assist plant supervision in correcting con-ditions that may compromise the safety of operations.
- Be onsite to provide appropriate assistance to the normal shift complement.
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Resconsibilities During transients and accidents, compare existing critical parameters (i.e. neutron power level; reactor coolant system level, pressure. and temperature; containm'ent pressure, temperature, humidity and radi-atien level; and plant radiation levels) with those predicted.in the Plant Transient and Accident Analysis to ascertain whether the plant is responding to the incident as predicted.
Report any abnormalities to the Shift Supervisor immediately and provide assistance in formulating a plan for appropriate corrective action.
Make a qualitative assessment of plant parameters during and following an accident in order to ascertain whether core damage has occurred.
During emergencies be ~ observant ' of critical parame-ters, ascertain that there is adequate core cooling
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including availability of a heat sink for the coolant system, and, in the event that critical parameters become unavailable due to instrument failure, perform calculations or through other means determine approxi-mate values for the parameters in question.
- Investigate the cause(s) of abnormal or unusual events occurring on assigned shift and assess any adverse effects therefrom. Recommend changes to procedures or equipment as necessary to prevent recurrence.
Evaluate the effectiveness of plant procedures in terms of terminating or mitigating accidents and make
, recommendations when changes are needed.
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' Perform an early review of the planned activities for the upcoming shift to ascertain whether special con-siderations or precautions are warranted and make appropriate; recommendations to the Shift Supervisor.
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Typical Collateral Duties
,i Assist the operations staff in interpreting and apply- M ing the requirements of Technical Specifications.
Evaluate effectiveness of plant instructions and re-commend needed changes to the appropriate Supervisor.
Evaluate core power distribution during and following load changes. . Perform hot channel factor and/or rod program analysis as required.
Prepare special safety-related reports.'
l Provide an engineering evaluation . of Licensee Event
, Reports as assigned and be ccgnizant of significant event occurrences within the industry through review l of appropriate reports available at the plant.
Accountability The STA is accountable for the following end results:
Contributes 'to maximizing safety of operations by independently observing plant status and advising the shift supervisor of conditions that could compromise plant safety.
Contributes to maximizing plant safety during tran-sient or accident situations by independently assess-
- ing plant conditions and by providing the technical
- assistance neccesary to mitigate the incident and ,
! minimize the effect on personnel, the environment, and i the public.
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- 5. GENERAL EDUCATION AND EXPERIENCE 5.1 EDUCATION AND TRAINING The Shift Technical Advisor should meet the education and training recommendations of Section 6.
- 5.2 EXPERIENCE N The STA candidate must complete the training and
- education specified in Section 6 and serve as a STA "in
- training" at the plant to which assigned for a minimum of 3 months. As a minimum, the candidate must have 1 year of nuclear power plant experience including at least 6 months onsite.
For a new plant, "in training" experience can be acquired during the plant startup testing program.
5.3 ABSENCES FROM STA DUTIES l Persons not performing the STA function or related work that keeps him/her abreast of plant conditions for a period of 4 months or longer should, prior to assuming the responsibilities of the position, receive the annual requalification training described in this document.
Revisions to emergency procedures and Technical Specification and modifications to safety-related systems should be reviewed prior to the STA assuming shift responsibilities.
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- 6. EDUCATION AND TRAINING REQUIREMENTS A < waiver for any of the required education and/or training
- should be granted only by the Manager of Nuclear Power and should be evaluated on a case-by-case basis. Such waivers may be considered when a candidate has documented accredited.
college courses or can demonstrate an acceptable level of j
knowledge through comprehensive examinations in the area to
- be waived.
For courses completed at an accredited college, a semester credit hour is considered equivalent to approximately 15 contact hours.
When courses prescribed in Sections 6.1.2 and 6.2 ' are not administered as part of an accredited program in a college or university, the curriculum shall be accredited by INPO when the accreditation program is implemented. I 6.1 EDUCATION 6.1.1 Prerecuisites Bevond Mich School Dioloma. It is i assumed that many candidates may have received previous training and are qualified to begin the
- coursework prescribed in 6.1.2. Prerequisite ,
j education considered necessary for successful j completion of the advanced coursework is identi- ;
fied below. This coursework may be waived without 4
l formal documentation of specific course comple-I tion.
l, Contact Hours j Mathematics Trigonometry, Analytical Geometry, 90
, College Algebra
,j Chemistrv
- Inorganic Chemistry 30-45 l ;
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Physics Engineering Physics (heat, 120-150 mechanics, light, sound, electricity and magnetism)
TOTAL 240-285 6.1.2 College Level Fundamental Education Contact Hours Mathematics 90 Engineering mathematics through the solution of first order linear differential equations associated with topics presented in this program.
Reactor Theorv 100 Atomic and Nuclear Physics, Statics, Dynamics, Point Kinetics, Reactivity Feedback Reactor Chemistrv 30 Inorganic Chemistry (as related.
to reactor systems)
Nuclear Materials 40 Strength of Materials Rea: tor Material Properties (phase diagrams, fuel densification)
Thermal Sciences (for nuclear systems) 120 Thermodynamics Laws of Thermodynamics P cperties of Water and Steam Steam Cycles and Efficiency Fluid Dynamics Bernoulli's Equation Fluid Friction and Head Loss Elevation Head Pump and System Characteristics Two Phase Flow Revision 1
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Heat Transfer Methods of Heat Transfer Boiling Heat Transfer Heat Exchangers Contact Hours
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Electrical Sciences 60 Electronics (Circuit theory, digital electronics)
Motors, Generators, Transformers, Switchgear Instrumentation and Control Theory Nuclear Instrumentation and Control 40 Radiation Detectors Reactor Instrumentation Reactivity Control and Feedback Nuclear Radiation Protection and Healen Physics 40 Biological Effects Radiation Survey Instrumentation Shielding TOTAL 520 6.2 APPLIED FUNDAMENTALS - PLANT SPECIFIC In addition to the general education requirements de-scribed in Section 6.1, all STAS shall complete the l following training at the college level tailored to the
! specific plant at which the STA is assigned or a plant of similar design. It.may be completed separately from or may be integrated with the education described in Section 6.1.
i Subject /Toeies Contact Hours i
Plant-Specific Reactor Technology (including core physics data)
Plant Chemistry and Corrosion Control 1
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Reactor Instrumentation and Control Reactor Plant Materials Reactor Plant Thermal Cycle
. TOTAL 120 6.3 MANAGEMENT / SUPERVISORY SKILLS Subiect Contact Hours Leadership Interpersonal Communication Motivation Problem and Decision Analysis i Directing Stress i
Human Behavior TOTAL 40 6.4 PLANT SYSTEMS The training program should cover the following systems along with others considered necessary for a specific plant.
System 7
Emergency Core Cooling Emergency Cooling Water Emergency Electrical Power, AC and DC Reactor Protection Reactor Coolant Reactor Coolant Inventory and Chemistry Control Containment System (including Containment Cooling)
Closed Cooling Water Nuclear Instrumentation Non-Nuclear Instrumentation Reactor Control i
Containment Hydrogen Monitoring and Control Radioactive Waste Disposal (liquid, gas, solid)
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Emergency Control Air Condensate and Main Feedwater Auxiliary Feedwater Steam Generator Level Control (PWR)
Reactor Vessel Water Level Control (BWR) ~
Main Steam Loose Parts Monitoring (PWR)
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,s Status Monitoring (including Process Computer)'
Seismic Monitoring '
t Residual Heat Removal Radiation Monitoring Plant Ventilation Main Turbine and Generator
-TOTAL 200 6.5 ADMINISTRATIVE CONTROLS Subiect Contact Hours 5
Responsibilities for Safe Operation and Shutdown Equipment Outages and Clearance Procedures Use of Procedures Plant Modifications Shift Relief Turnover and Mcnning Containment Access Maintaining Cognizance of Plant Status l
Unit Interface Controls (multi-unit plants with one or more units still under construction)
Physical Security- N Control Room Access Administrative Requirements of the STA Radiological Emergency Plan Title 10 Code of Federal Regulations (appropriate sections)
! Plant Technical Specifications (including bases;
'I Radiolcgical Control Instr;tetions 4
TOTAL 80
- 6.6 GENERAL OPERA, TING PROCEDURES i
Subiect Contact Hours Startup '
Power Operations s Shutdown Xenon-Following While on Standby ECP and S.D. Margin Calculation Others as Appropriate for the Station ,
TOTAL _,
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6-c 6.7 TRANSIENT / ACCIDENT ANALYSIS AND EMERGENCY PROCEDURES
- Subiect Contact Hours Transient and Accident Analyses Plant Abnormal and Emergency Procedures emphasizing the STA role TOTAL 30-45 ,
'! 6.8 SIMULATOR TRAINING '-
The plant evolutions, transients and events listed below should be conducted along with any others deemed nec-essary. The primary objective should be to demonstrate plant and operator response to a given condition or event and not to develop the control manipulation expertise of the trainee. The trainee / instructor ratio should not exceed 4:1 except when the " Team Training" concept is .
l being utilized.
Simulator excercises should be preceded by a period of discussion of the planned exercises addressing expected response of tne plant and applicable plant procedures to be used. Approximately 100 contact hours are . required with about 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> in the classroom and 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> on the simulator.
Follcwing each exercise demonstrating a transient or emergency event, an incident critique discussion should I be held to enhance the trainees' understanding of that particular exercise. When the simulator is not plant-specific, the training should be tailored to the specific j plant as much as practical.
I PWR Simulator Exercises Reactor and Plant Startup
- i Load Changes at Power
. Shutdown to Cold Condition Demonstration of Steam Generator Level Manual Control Loac Rejections of Greater than 104 Pevision 1 wm - , , , , - , - - . , , , - - . , p - - - , - . - - - ,, , , . - ,, ,-----n- ,,,.,,-,.,,--,g - - - , .-- _,
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'le Failure of Rod Control System Failure of Automatic Steam Generator Level. Controls Failure of Pressurizer Level and Pressure Automatic Controls Turbine Trip from Full Power Reactor Trip from Full Power Loss of Normal Feedwater at Full Power Failure Open of Power Operated Relief Valve Stuck Open Pressugizer Safety _ Valve Loss of Reactor Chlant Pumps at Full Power and Demonstration of Natural Circulation Failure Open of One or More Turbine Bypass Valves While at a) Full Power, b) Hot Standby Loss of All Feedwater (normal and emergency)
Loss of Reactor Coolant (small and DBA)
. Steam Generator Tube Rupture (small and large)
Loss of RHR Shutdown Cooling with the RCS Temperature 200 to 3000 F Inadvertent Safety Injection While at Power Loss of Offsite Electrical Power Loss of One Train of Onsite Electrical Power BWR Simulator Exercises ,
I Reactor and Plant Startup j
Load Changes at Power (using flow control when applicable) '
Shutdown >
Load Rejection of Greater than,10%
Turbine Trip from Full Power .
i .,- Turbine Bypass Valve Failure to Open Fo11cwing Trip Inadvertent Closure of MSIV's While at Power Reactor Scram from Full Power Reactor Pressure Control Failure Dropped Control Rod While at Power Cold Water Transient at Power '
Inadvertent Opening of Relief Valve Loss of Main Feedwater Pumps at Power Inadvertent Start of Idle Recirculation Pump Inadvertent Trip of Recirculation Pump (s)
Loss of Reactor Coolant (small break - large break)
Steam Line Break (inside-outside containment)
Loss of Offsite Power Loss of Shutdown Cooling with RCS Temperature 200 - 300 F Demonstration of Natural Circulation Capabilities c Malfunction of Reacror Water Level Automatic Controls l.
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- 6.9 ANNUAL REQUALIFICATION TRAINING Subiect Material Hours Recuired i Review of transient and accident analyses emphasizing the individual's role in accident assessment. Review selected industry events and - LER's that could have led to more serious incidents.
40 Simulator exercises related to the transients and plant evolutions in Section 6.8 conducted so as to emphasize the STA role. Best results will be achieved ' when participating in exercises with a shift operating crew utilizing the " Team Trainina" '
concept. 20 (Direct interaction with i
1 the simulator) 4 carticipation in a program that will ensure cognizance of plant modifica-tions and procedure changes.
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