tnat riga
TRANSCRIPT
Training Needs Analysis
TRIGA MARK Research Reactor Facility
Education and Training Center National Nuclear Energy Agency
Indonesia
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 2 of 20 National Nuclear Energy Agency (BATAN)
A. Introduction
1. Background
Based on the IAEA Guideline on The Education and Training Review Service,
any nuclear installations should develop and maintain a sustainable and
adequate education and training program in nuclear safety, consistent with
the IAEA safety standards and good international practices with due
recognition to national conditions.
In order to ensure that the adequate competence are achieved and
maintained, nuclear installations should define a well training program for its
staff. It is essential that systematic approach to training (SAT) be applied in
design, develop and implement the training program.
For many years BATAN had designed, developed, and implemented several
training course on nuclear technology as well as in nuclear safety, but we had
not implemented the SAT methods as a whole, especially on the first step i.e.
the training needs analysis. In 2002, the IAEA education and training review
team conclude that nuclear facilities in BATAN need a systematic approach to
training, including a systematic self-assessment of competencies and training
needs in co-operation with the education and training center.
IAEA also published some documents related to the competency
requirements especially for research reactor personnel as well as the
guideline to assess the competency of personnel. These IAEA documents
should be used as a reference to carry out the training needs analysis for
research reactor personnel.
2. Objective
The objective of this activity is to conduct the training needs analysis
according to the IAEA guideline. The result can be used either by the reactor
facility to propose annual training program or by the Education and Training
Center to set up the training program.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 3 of 20 National Nuclear Energy Agency (BATAN)
3. Scope
The training needs analysis is implemented to the nuclear facilities that
operate the TRIGA MARK research reactor i.e. the Center for Research and
Development of Advanced Technology (P3TM) at Yogyakarta and the Nuclear
Technology Research and Development Center (P3TKN) at Bandung.
Only three fields of work (division) are assessed: division of reactor operation,
reactor safety, and reactor maintenance.
4. Methodology
Based on the IAEA guidance, training needs analysis can be conducted
following the steps below.
Figure 1: Training Needs Assessment Steps
Identification of Unit Responsibilities
Description of Job Positions in relevant
Units
Description of Competencies for each
Job Position
Gap Analysis
Organizational Mandate / Flow Chart
Expertise of Manager/Senior Staff
Expertise of Manager/Senior
Staff
Expertise of Manager/Senior
Staff
Expertise of Manager/Senior Staff & Survey
List of Units with corresponding
Functions
List of Duties for each position in relevant
Units
List of Required competencies for each
positions
List of competencies needing additional
Training (initial/continuous)
Design: building new TP/Reviewing & Improving existing TP
Step 1
Step 2
Step 3
Step 4
Step 5
Identification of Unit Responsibilities
Description of Job Positions in relevant
Units
Description of Competencies for each
Job Position
Gap Analysis
Organizational Mandate / Flow Chart
Expertise of Manager/Senior Staff
Expertise of Manager/Senior
Staff
Expertise of Manager/Senior
Staff
Expertise of Manager/Senior Staff & Survey
List of Units with corresponding
Functions
List of Duties for each position in relevant
Units
List of Required competencies for each
positions
List of competencies needing additional
Training (initial/continuous)
Design: building new TP/Reviewing & Improving existing TP
Step 1
Step 2
Step 3
Step 4
Step 5
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 4 of 20 National Nuclear Energy Agency (BATAN)
Step 1
The organizational mandate should take into account the present needs as
well as the future aspirations of the organization.
The list of units should be presented with corresponding functions. It does
not matter if some of the units may not be in place at the time of self-
assessment, however their need may be accounted for in the development
of training program.
The information required for this step is usually available in the Quality
Assurance Manual of each facility and in IAEA draft Safety Series DS 325
for research reactor operating organizations.
Step 2
Describe the job positions. If the job position do not exist then it may be
useful to define the job positions and the prerequisites such as academic
and professional background.
Describe duties for each job positions. Typical duties in regulatory body
can be found in IAEA draft Safety Series DS 325.
Step 3
Taking into account the job positions and corresponding duties, relevant
competencies should be identified. This is a time consuming task and it is
suggested that this may be effectively done in a group exercise composed
of subject matter specialist, supervisor, trainer and the incumbent of that
position.
Step 4
Taking into account the professional and academic background of the
staff, evaluate the existing competencies for the job positions to determine
the existing gaps. It is suggested that this task be performed by the same
group of people as in step 3 for consistency. To facilitate the execution of
this step, the questionnaires are needed to be developed.
Step 5
Once the competency gaps are identified, the training modules can be
designed or existing training modules can be refined, accordingly.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 5 of 20 National Nuclear Energy Agency (BATAN)
B. Organization Aspect BATAN owns and operates two TRIGA MARK research reactors, one in the
Center for Research and Development of Advanced Technology (P3TM) at
Yogyakarta and another in the Nuclear Technology Research and
Development Center (P3TKN) at Bandung.
1. Center for Research and Development of Advanced Technology (P3TM)
The Nuclear Research Center in Yogyakarta was constructed in 1974,
occupying an area of 8.5 hectares. It is where the Center for Research and
Development of Advanced Technology (P3TM) which operates Kartini
Reactor, a Triga Mark Research Reactor, located. The Kartini Reactor
achieved its first criticality in 1979 with a capacity of 100 kW and is in
operation to date.
Organizational Structure of P3TM
P3TM has some other tasks and responsibilities besides operating the
research reactor; therefore it has more divisions in its organizational
structure as presented in attachment 1.
Task and Responsibility
P3TM has a role to implement research and development of advanced
technology. In order to achieve its mission, P3TM has several functions
as follows:
• research and development in the field of physics and chemistry,
• research and development in the field of low and medium energy
particle accelerator;
• research and development in the field of process technology;
• research reactor operation, maintenance and utilization;
• occupational safety control and health services;
• administration affairs; and
• nuclear safety and security and security management.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 6 of 20 National Nuclear Energy Agency (BATAN)
This training needs assessment concerns only to functions related to
the research reactor operation, maintenance and safety, therefore it is
focused to only two divisions. (Blue color in Organizational Structure of
P3TM, attachment 1).
1. Reactor Division
The Main Functions:
a. operation, maintenance and utilization of reactor;
b. measurement and evaluation of safety data, and also
management of reactor fuel element and safeguard.
Divided into two sub divisions:
1.1. Reactor Operation and Utilization Sub Division
The main tasks:
a. to prepare the utilization license of the reactor;
b. to operate, maintain, and utilize the reactor;
c. to provide irradiation services;
d. to serve safety inspection by the authorities.
1.2. Reactor Physics and Technology Sub Division
The main tasks:
a. to measure and evaluate: neutronic, thermohydrolic, water
chemistry, component of reactor and whole entire reactor safety
parameter data;
b. to conduct research and development in the field of reactor
physics and technology;
c. to manage reactor fuel element and safeguard, and serve safety
inspection by the authorities;
d. to develop reactor operation and utilization of the facility safety.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 7 of 20 National Nuclear Energy Agency (BATAN)
2. Health and Safety Division
The Main Functions:
a. radiation protection and occupational safety control;
b. waste management and environment safety control;
c. health services and nuclear emergency response.
Divided into two sub divisions:
2.1. Radiation Protection and Occupational Safety Sub Division
The main tasks:
a. to control personnel radiation dose;
b. to monitor and control the working area;
c. to take action in case of radiation and non radiation work
accident;
d. to plan and implement the nuclear and non nuclear emergency
response program;
e to control the distribution of radioactive material on the facility
environment;
f. to arrange the utilization, storage and operation license of
nuclear material.
2.2. Waste management and Environmental Safety Sub Division
The main tasks:
a. to manage radioactive and hazardous waste before it is sent to
the Center for Development of Radioactive Waste Management;
b to monitor and control environmental safety.
2.3. Health and Nuclear Emergency Sub Division
The main tasks:
a. to give technical aids and health care in the Facility;
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 8 of 20 National Nuclear Energy Agency (BATAN)
b to conduct health examination of radiation worker in the facility
and manage their medical records;
c to evaluate, supervise nuclear and non nuclear emergency
medical response.
Human Resources
The total number of people who work at the Center for Research and
Development of Advanced Technology (P3TM) is 468 persons with the
distribution of age and education as in the following table.
Table 1: the distribution of manpower at P3TM
Among of them, there are 13 persons have qualification as reactor
supervisors, 9 have reactor operator qualification, and 5 persons as
radiation protection officers (RPO). The above licenses are issued by
the national regulatory body (BAPETEN).
Ages Category Number of Employee
High School
Diploma Under Graduate
Master Doctor
30 - 34 8 7 1
35 - 39 44 16 22 5 1
40 - 44 127 66 36 18 5 2
45 - 49 196 113 22 46 13 2
50 - 54 72 35 8 24 4 1
55 - 59 19 10 8 1
60+ 2 2
TOTAL 468 240 95 103 25 5
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 9 of 20 National Nuclear Energy Agency (BATAN)
2. Center for Research and Development of Nuclear Techniques
The Center for Research and Development of Nuclear Techniques (P3TKN)
was constructed in 1967, and occupying an area of 3 hectares in Bandung.
This is the place where the first reactor was build and operated in Indonesia.
The TRIGA Mark II reactor originally had 250 KW power, and was increased
to 1000 kW in 1971, and then was upgraded again to 2000 kW in the year
2000. Therefore the reactor now is called TRIGA 2000.
Organizational Structure
P3TKN has some other tasks and responsibilities besides operating of
the research reactor; therefore it has more divisions in its
organizational structure as presented in attachment 2.
Task and Responsibility
P3TKN has a role to implement research and development of nuclear
techniques. In order to achieve its mission, P3TKN has several
functions as follows:
• research and development in the field of base material
• research and development in the field of labeled compounds
• research and development in the field of instrumentation and
radiometry analytical techniques
• reactor operation, maintenance and utilization
• occupational safety control and health services
• administration affairs
• nuclear security and safety management
This training needs assessment concerns only to functions related to
the research reactor operation, maintenance and safety, therefore it is
focused to only two divisions. (Blue color in Organizational Structure of
P3TKN, attachment 2).
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 10 of 20 National Nuclear Energy Agency (BATAN)
1. Reactor Division
The Main Functions :
a. operation, maintenance and utilization of reactor
b. measurement and evaluation of safety data, and also
management of reactor fuel element and safeguard
Divided into two sub divisions:
1.1. Reactor Operation and Utilization Sub Division
The main tasks:
a. to prepare the utilization license of the reactor
b. to operate, maintain, and utilize the reactor
c. to provide irradiation services
d. to serve safety inspection by the authorities
1.2. Reactor Physics and Technology Sub Division
The main tasks:
a. to measure and evaluate: neutronic, thermohydrolic, water
chemistry, component of reactor and whole entire reactor safety
parameter data
b. to conduct research and development in the field of reactor
physics and technology
c. to manage reactor fuel element and safeguard and serve safety
inspection by the authorities
d. to develop reactor operation and utilization of the facility safety
2. Health and Safety Division
The Main Functions:
a. radiation protection and occupational safety control
b. waste management and environmental safety control
c. health services and nuclear emergency response
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 11 of 20 National Nuclear Energy Agency (BATAN)
Divided into three sub divisions:
2.1. Radiation Protection and Occupational Safety Sub Division
The main tasks:
a. to control personnel radiation dose
b. to monitor and control the working area
c. to overcome radiation and non radiation work accident
d. to plan and implement the nuclear and non nuclear emergency
response program
e. to control the distribution of radioactive material on the facility
environment
2.2. Waste management and Environmental Safety Sub Division
The main tasks:
a. to manage radioactive and hazardous waste before it is sent to
the Center for Development of Radioactive Waste Management
b. to control environmental safety
2.3. Health and Nuclear Emergency Sub Division
The main tasks:
a. to give technical aids and health care in and around the facility
b. to conduct health examination to radiation workers in the facility
and manage their medical records
c. to evaluate, supervise nuclear and non nuclear emergency
medical response
Human Resources
The total number of people who work at the Center for Research and
Development of Nuclear Techniques (P3TM) is 210 persons with
distribution of age and education as in the following table.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 12 of 20 National Nuclear Energy Agency (BATAN)
Table 2: the distribution of manpower at P3TKN
Among of them, there are 8 persons have qualification as reactor supervisor,
18 have reactor operator qualification, and 6 persons as radiation protection
officers (RPO). The above licenses are issued by the national regulatory body
(BAPETEN).
Ages Category Number of Employee
High School
Diploma Under Graduate
Master Doctor
20 - 24 1 1
25 - 29 1 1
30 - 34 8 5 1 2
35 - 39 20 10 6 4
40 - 44 50 26 3 12 8 1
45 - 49 64 37 16 9 2
50 - 54 44 25 1 11 5 2
55 - 59 16 6 4 3 3
60+ 6 4 3 3
TOTAL 210 109 6 54 34 11
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 13 of 20 National Nuclear Energy Agency (BATAN)
C. Competency Level Assessment In order to assess competency level of personnel required in research reactor,
as well as the existence competency level, we divided the activity into three
phases, i.e. implementation of the workshop; distribution the questionnaire to
the respondent and collection; and then performing the analysis itself.
1. Workshop on Training Needs Assessment
The workshop on Training Needs Assessment was conducted on March 28 to
April 1, 2005 at the Education and Training Center, Pasar Jumat, Jakarta. The
workshop was attended by 15 senior staff from BAPETEN (regulatory body),
research reactor facilities, nuclear safety center, human resource
development bureau, and education and training center. The schedule and list
of participants can be found in attachment 3 and attachment 4.
Objectives of Workshop
The first objective is to introduce the methodology on performing the training
needs assessment based on the IAEA guidance. Second is to compose a list
of competency requirement for personnel, who work as reactor operator and
supervisor, reactor safety, and reactor maintenance. Even though the IAEA
had prepared a list of competency for research reactor, in this workshop the
participants were requested to analyze and revise it, if necessary, to fit into
Indonesian condition.
Four Quadrant Competency Framework
IAEA has proposed a competency framework based on four quadrants. This
framework divides the competencies required by research reactor into four
categories (level I) and each category has some more detail sub categories
(level II).
The first quadrant: Basic Technical Competency includes competencies
related to the general knowledge, basic of radiation, nuclear safety and basic
concept of nuclear reactor. The second quadrant: Specific Competency on
Research Reactor includes competencies related to research reactor
technology, reactor experimental facility and operation of research reactor.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 14 of 20 National Nuclear Energy Agency (BATAN)
Third quadrant: Regulation and Administration comprises competencies
related to the regulation system and quality management. The fourth
quadrant: Personal and Interpersonal Effectiveness covers competency on
decision-making, communication, team work and project management. The
four-quadrant competency (level I, and II) can be found in attachment 5.
Totally, there are 62 types of competencies, which distributed into those four
quadrants. The list of personnel competency of research reactor facility can
be found in the questionnaire (attachment 6).
Level of Competency
During the workshop participants discussed and agreed upon the level of
competency with its criteria as follow:
High: the competence is absolutely needed to perform the task.
Lacking of this competency will cause failure of task performance. The
personnel should have cognitive or psychomotor aspect at least in the
level of “synthesis” or “evaluation”.
Medium: the competence is needed to perform the task. Lacking of
this competency will probably descent task performance. The
personnel should have cognitive or psychomotor aspect in the level of
“application” or “analysis”.
Low: the competence is not really needed to perform the task. Lacking
of this competency will not harm but existing competency could raise
task performance. The personnel should have cognitive or
psychomotor aspect just enough in the level of “knowledge” or
“comprehension”.
Not available: the competence is not needed to perform the task.
In order to analyze the competency level quantitatively, those levels above
are converted to numerical value, high equals 3, medium equals 2, low equals
1, and not available is zero.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 15 of 20 National Nuclear Energy Agency (BATAN)
Type of Work and Level of Personnel
During the workshop participants discussed and agreed upon the type of work
in research reactor which will be assessed, as follows:
• reactor operation,
• reactor safety, and
• reactor maintenance.
And level of personnel is categorized into two groups:
• Senior, who has work experience more than 15 years and
• Junior, who has work experience less than 15 years.
2. Questionnaire Distribution and Collection
The process of distribution and collection the questionnaire was carry out in
May – June 2005, covers three research reactors in Yogyakarta, Bandung,
and Serpong. According to its similarity, we analyze the respondents from
Yogyakarta and Bandung in the same project, on the other hand the
respondents from Serpong will be analyzed separately.
Type of Questionnaire
The questionnaire were presented in two types, first was in hard-copy form.
The respondents were requested to fill a tick mark ( ) on the appropriate
column of their answer (see the attachment 6). The second form was a
package program (software). The respondents work in front of their computer
and fill the questionnaire by clicking the mouse. Display of the user interface
program can be seen in attachment 7.
Actually we prefer to use only the second approach that is using package
program, since each question is presented one by one, the interfere from
previous answers and following questions can be avoided. But due to the
limited computer availability, some respondents preferred to use the hardcopy
form.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 16 of 20 National Nuclear Energy Agency (BATAN)
Respondents
There are total 73 respondents, to get factual and ideal competency level,
from the Center for Research and Development of Advanced Technology
(Yogyakarta) and 130 respondents from the Center for Research and
Development of Nuclear Techniques (Bandung). Some senior staffs were
requested to fill more than one questionnaire, ideal and factual competency
level for senior as well as junior personnel. The following table represents
distribution of the respondents, which are compilation of respondents from the
Center for Research and Development of Advanced Technology (Yogyakarta)
and the Center for Research and Development of Nuclear Techniques
(Bandung).
Table 3: distribution of respondents
P3TM P3TKN TotalOperation Senior 5 10 15Operation Junior 9 13 22Safety Senior 8 12 20Safety Junior 6 6 12Maintenance Senior 3 8 11Maintenance Junior 10 8 18
Number of Factual DataType and Level of Respondents
P3TM P3TKN TotalOperation Senior 5 12 17Operation Junior 5 10 15Safety Senior 8 17 25Safety Junior 8 13 21Maintenance Senior 3 12 15Maintenance Junior 3 9 12
Type and Level of Respondents
Number of Ideal (Needed) Data
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 17 of 20 National Nuclear Energy Agency (BATAN)
3. Gap of Competency Analysis
Based on the returned questionnaires, the personnel competencies have
been available in the research reactor facilities are presented in Attachment 8.
The gap of competencies: specific competencies level 3, level 2 and level 1
are tabulated and presented as a graph also in Attachment 8 ~ 13.
Level 3 is the averages values of specific competencies listed in the
questionnaires, which are filled by the respondents. Level 2 is the averages
value of the level 3 competencies in the respected sub quadrant. Level 1 is
the each quadrant average value.
There are three criteria of gap for each specific competency: A, B, and C.
Criteria A: value of the gap bigger than 0,5
Criteria B: value of the gap less than 0,5
Criteria C: value of the gap negatives.
The specific competencies that have criteria A are urgently eliminated and
specific related training course are badly needed to be conducted for those
personnel (as soon as possible). Criteria B should be eliminated by
implemented specific related training course. Criteria C means that the
competencies have been achieved therefore a refreshment course are
needed to maintain their competencies.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 18 of 20 National Nuclear Energy Agency (BATAN)
D. Training Module Identification The Education and Training Center of BATAN, which is established in 1981,
had conducted several training courses; even they were not fully designed as
recommended by SAT. The figures bellow present the number of training
course which were conducted since 1982 and the number of participants
categorized by the topics of the training course.
Table 4: number of training course per year
Table 5: number of participants
381
728835
2986
4443
1031
214
0
500
1000
1500
2000
2500
3000
3500
4000
4500
Num
ber o
f Par
ticip
ants
Nuclear Materialand Fuel
Informatics NuclearInstrumentationand Instalation
Nuclear andRadiation Safety
Application ofRadioisotope and
Radiation
Nuclear Reactorand Energy
Material Science
3
6
1
24
18
23 23
14
21
24
19
12
33
2022 22
43
20
2728
22
44
37 37
0
5
10
15
20
25
30
35
40
45
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 19 of 20 National Nuclear Energy Agency (BATAN)
The training courses and correlated subjects, which are assumed can fulfill
the gap of competencies is tabulated in attachment 14.
Even though several trainings are readily available, or have been conducted
for sometimes, they must be reviewed and validated to recent requirements.
On the other hand, there is still lack of training courses for some
competencies, particularly in quadrant 4 (personal and interpersonal
effectiveness). Therefore it is needed to designed new training courses to
fulfill these gaps.
V. Conclusion The analysis of competency gap has been performed following the IAEA
guidance on Systematic Approach to Training and based on the drafts IAEA
documents No. DS 325 with some modifications to suit BATAN’s conditions.
The analysis is performed for three fields of work in TRIGA MARK research
reactor facilities:
reactor operation,
reactor safety, and
reactor maintenance.
With two levels of personnel, senior who has more than 15 years working
experience, and junior who has less than 15 years working experience. The
respondents are originated from BATAN’s research reactor facility in
Yogyakarta (P3TM) and Bandung (P3TKN).
Based on the result of competency gap analysis (attachment 8 to 13) there
are some specific competencies for particular group of personnel, which have
to be urgently eliminated (criteria A), should be eliminated (criteria B), and just
needed refreshing (criteria C).
Training courses that are needed to bridge most specific competency gap are
available, or have been conducted for sometimes and some training courses,
especially for quadrant 4 are inadequate.
Training Needs Analysis TRIGA MARK Research Reactor Facility
Education and Training Center 20 of 20 National Nuclear Energy Agency (BATAN)
Since this activity is the first trial, some recommendations need be followed
up:
Review and evaluate the method used for collecting data of personnel
competency level.
Validate the collected data of personnel competency level.
Validate the available training courses and design new training courses
that require to bridge the gap of competency.
Perform the similar analysis for other facilities.
Attachment 1 Organizational Structure of P3TM
Correspondence, Officialdom, and Scientific Doc Sub Division Ø Management
• Human Resource • Records • Secretariat • Information and Documentation
Financial Sub Division Ø Management
• Finance
Equipment and Supply Sub Division Ø Management
• Infrastructure and Equipment
Administration Affairs ο Supplement
Ø Management
Physical and Chemical Technology Div ο Nuclear Fuel and Material
Ø Reactor, Nuclear and Developing Material
Ø Reactor, Nuclear and Developing Material • Material Modification and Engineering • Material Characterization Techniques
Ø Installation • Accelerator Installation
Ø Instrumentation • Detection and Perception Techniques • Acquisition, Processing and Imaging Techniques • Control, Processing Control and Actuation Techniques
Ø Electro mechanics • Apparatus System • Lifting and Transportation System • Cooling and Heater System • Power System • Motor System
Accelerator Division ο Nuclear Installation and Instrumentation
Ø Installation Ø Instrumentation Ø Electro mechanics
Processing Technology Division ο Nuclear Fuel and Material
Ø Nuclear Fuel Ø Radioactive Waste
Ø Nuclear Fuel • Nuclear Fuel Purification and Conversion Techniques
Ø Radioactive Waste • Radioactive Waste Processing Techniques
Reactor Division ο Reactor and Nuclear Energy
Ø Nuclear Reactor Technology ο Radiation and Nuclear Safety
Ø Safeguard
Reactor Operation and Utility Sub Division Ø Nuclear Reactor Technology
• Physics of Nuclear Reactor Core • Nuclear Reactor Instrumentation and Control System • Nuclear Reactor Processing System • Operation and Maintenance of Nuclear Reactor • Nuclear Reactor Utility
Ø Safeguard • Physical Protection Technology
Reactor Physics and Technology Sub Division Ø Nuclear Reactor Technology
• Physics of Nuclear Reactor Core • Nuclear Reactor Instrumentation and Control System • Nuclear Reactor Processing System • Operation and Maintenance of Nuclear Reactor • Nuclear Reactor Utility
Health and Safety Division ο Radiation and Nuclear Safety
Ø Radiation Safety Ø Environmental Safety Ø Installation Safety
ο Supplement Ø Management
Radiation Protection and Occupational Safety Sub Division Ø Radiation Safety
• Radiation Protection
Waste Management and Environmental Safety Sub Division Ø Installation Safety
• Non Nuclear Installation Safety Ø Environmental Safety
• Environmental Radiation Safety
Health and Nuclear Emergency Preparedness and Response Sub Div Ø Management
• Health Services Ø Radiation Safety
• Radiation Emergency Preparedness and Response
Library Unit ο Supplement
Ø Informatics
Nuclear Security Unit ο Supplement
Ø Management
Ø Informatics • Library
Ø Management • Security
Ø Instrumentation • Detection and Perception Techniques • Acquisition, Processing and Imaging Techniques • Control, Processing Control and Actuation Techniques
Ø Electro mechanics • Apparatus System • Lifting and Transportation System • Cooling and Heater System • Power System • Motor System
Electro mechanical Workshops ο Nuclear Installation and Instrumentation
Ø Instrumentation Ø Electro mechanics
Center for Research and Development of Advanced
Technology
Attachment 2 Organizational Structure of P3TKN
Correspondence, Officialdom, and Scientific Doc Sub Division Ø Management
• Human Resource • Records • Secretariat • Information and Documentation
Ø Informatics • Library
Financial Sub Division Ø Management
• Finance
Equipment and Supply Sub Division Ø Management
• Infrastructure and Equipment
Administration Affairs ο Supplement
Ø Management Ø Informatics
Base Material Division ο Nuclear Fuel and Material
Ø Nuclear Fuel Ø Reactor, Nuclear and Developing
Material ο Supplement
Ø Informatics
Ø Nuclear Fuel • Nuclear Fuel Synthesize Technique and
Engineering Ø Reactor, Nuclear and Developing Material
• Material Characterization Techniques Ø Informatics
• Nuclear Data
Ø Radioisotope Process • Nuclear Analysis Technique
Ø Instrumentation • Detection and Perception Techniques • Acquisition, Processing and Imaging
Techniques • Control, Processing Control and Actuation
Ø Electro mechanics • Apparatus System • Lifting and Transportation System • Cooling and Heater System • Power System
Labeled Compound Division ο Isotope and Radiation
Ø Labeled Compound Process
Instrumentation and Radiometry Analysis Technique ο Isotope and Radiation
Ø Radioisotope Process ο Nuclear Installation and Instrumentation
Ø Instrumentation Ø Electro mechanics
Ø Labeled Compound Process • Labeled Compound and Radio pharmacy
Technique • Radio pharmacology • Radio Immunoassay Technique
Reactor Division ο Nuclear Reactor and Energy
Ø Nuclear Reactor Technology ο Radiation and Nuclear Safety
Ø Safeguard
Reactor Operation and Utility Sub Division Ø Nuclear Reactor Technology
• Physics of Nuclear Reactor Core • Nuclear Reactor Instrumentation and Control • Nuclear Reactor Processing System • Operation and Maintenance of Nuclear Reactor • Nuclear Reactor Utility
Ø Safeguard • Physical Protection Technology
Reactor Physics and Technology Sub Division Ø Nuclear Reactor Technology
• Physics of Nuclear Reactor Core • Nuclear Reactor Instrumentation and Control • Nuclear Reactor Processing System • Operation and Maintenance of Nuclear Reactor • Nuclear Reactor Utility
Health and Safety Division ο Radiation and Nuclear Safety
Ø Radiation Safety Ø Environmental Safety Ø Installation Safety
ο Supplement Ø Management
Radiation Protection and Occupational Safety Sub Division Ø Radiation Safety
• Radiation Protection
Waste Management and Environmental Safety Sub Division Ø Installation Safety
• Non Nuclear Installation Safety Ø Environmental Safety
• Environmental Radiation Safety
Health and Nuclear Emergency Preparedness and Response Ø Management
• Health Services Ø Radiation Safety
• Radiation Emergency Preparedness and Response
Nuclear Security Unit ο Supplement
Ø Management
Ø Management • Security
Center for Research and Development of Nuclear Technique
Monday Tuesday Wednesday Thursday Friday28-Mar-05 29-Mar-05 30-Mar-05 31-Mar-05 1-Apr-05
08.00 ~ 08.45 Opening CeremonyThe Operating Organization of
Research Reactor
Four quadrant Competencies(Hendriyanto)
Existing Competencies(Hendriyanto)
Seminar and Discussion
08.45 ~ 09.30Course Introduction
(Hendriyanto)
(Naek Nababan)
idemidem idem idem
09.45 ~ 10.30IAEA Policy in
Education Training(Eko Y. Winarno)
idemWorking Group: Four
quadrant Competencies
Working Group: Existing Competencies
idem
10.30 ~ 11.15 idemSafety Requirements of
Research Reactor(Anhar R.A.)
idem idem idem
11.15 ~ 12.00Systematic Approach to
Training(Rini Rindayani)
idem idem idem
13.00 ~ 13.45 idem idemWorking Group:
Needed CompetenciesWorking Group:
Gap CompetenciesConclusion
(Hendriyanto)
13.45 ~ 14.30Needs Analysis
(F. Basuki)
Job Analysis of BATAN's Reactor
(Hisyam Said)idem idem
Course Evaluation(Div. Of Evaluation)
14.45 ~ 15.30 idem idem idem idemClosing Ceremony(Director of E&T)
Schedule of WorkshopTraining Needs Assessment in Nuclear Safety
Jakarta, 28 March - 1 April 2005
Coffee Break
Coffee Break
Lunch Break
Time
Attachment 3
Attachment 4
NO Name of Participants Organization
1 Reinaldy NazarCenter for Research and Development of Nuclear
Techniques (Bandung)
2 Agus Rakhim, STCenter for Research and Development of Nuclear
Techniques (Bandung)
3 Ir. SuyamtoCenter for Research and Development of Advanced
Technology (Yogyakarta)
4 Drs. A. MariatmoCenter for Development of Research Reactor
Technology (Serpong)
5 Ir. Yusi Eko Yulianto, Dipl.Eng.Center for Development of Research Reactor
Technology (Serpong)
6 Sudijono, ST.Center for Development of Research Reactor
Technology (Serpong)
7 Dr. M. Dhandhang PurwadiCenter for Development of Research Reactor
Technology (Serpong)
8 Ir. Djen Djen Djaenal, M.Eng.Center for Development of Nuclear Safety Technology
(Serpong)
9 Ir. Andajani Muljanti National Regulatory Body (BAPETEN)
10 Ir. Lukman Hakim National Regulatory Body (BAPETEN)
11 Dra. Djuartini Saleh Education and Training Center
12 Indragini, S.Si. Education and Training Center
13 Dra. Endang Khristuti Education and Training Center
14 Drs. M. Zainuddin Education and Training Center
15 Dra. Rina Godiani Human Resources Development Bereau
List of Participants
28 March ~ 1 April 2005Workshop on Training Needs Assessment in Nuclear Safety
Attachment 5
Q1 Basic CompetencyQ1.1 Basic - General Knowledge
Q1.2 Basic Knowledge on Radiation
Q1.3 Basic Knowledge on Nuclear Safety
Q1.4 Basic Knowledge on Nuclear Reactor
Q2 Specific Competency on Research Reactor FacilityQ2.1 Research Reactor Technology
Q2.2 Experimental Facility in Research Reactor
Q2.3 Operasion of Research Reactor
Q3 Regulation and AdministrationQ3.1 Rules and Regulation System
Q3.2 Quality Assurance
Q4 Personal and Interpersonal EffectivenessQ4.2 Decision Making
Q4.3 Communication
Q4.4 Team Work
Q4.5 Project Management
Four Quadrant CompetencyPersonnel of Research Reactor Facility
(Workshop Training Needs Analysis, rev. April 2005)
Attachment 6
Name of Respondent:Field of Work: Operation / Safety / MaintenancePersonnel Level: Senior / Junior
High Medium Low N.A.Q1: Technical Competency1.1. General Backround Knowledge
1 Understanding of industrial safety procedures at work.2 Application of first aid.3 Understanding and application of plant fire protection plan and
fire drills4 Understanding of facility security procedures5 Understanding electricity and electronics techniques6 Ability to read and interpret technical drawings.7 Demonstrated ability to use modern computing systems.8 Ability to implement the safety culture
Basic Knowledge of Radiation9 Understanding of fundamentals of nuclear physics including
quantities, units and symbols, structure of the atom andradioactive decay, interaction of radiation with matter.
10 Understanding of radiation safety principles and procedures(e.g. Principles of radiation protection, exposure limits andmeans of protection, sources of radiation in research reactors,and Principles of shielding)
11 Comprehension of radiation monitoring methods and surveyequipment and their use.
12 Understanding of radiation effects to human body
Basic Kowledge of Reactor13 Understanding of fundamentals of reactor theory, including
fission process, neutron multiplication, source effects, controlrod effects, criticality indications, reactivity coefficient andpoison effects.
14 Comprehension of heat transfer, thermodynamic and fluidmechanics ( e.g. pressure drop, orifice measurement, pumpcavitations, mechanism of heat transfer from cladding tocoolant, heat exchanger, natural circulation etc.)
15 Understanding of materials and their behaviour in radiationfield and their aging.
Competency
Questionaire on Personal Competency
Level
High Medium Low N.A.Competency Level
Nuclear Safety16 Understanding of nuclear safety principles including defence in
depth, core inventory of radioactive nuclide, role of successivebarrier and mitigation of radiological consequences, hazardsinvolved in the use of nuclear energy, concepts of normal,abnormal and incidents etc.
17 Capability to review the safety analysis report as required.18 Understanding and demonstrated ability of nuclear material
accountability19 Understanding of nuclear emergency preparedness and
response
Q.2. Facility Specific CompetencyTechnology of Research Reactor
20 Understanding of general features of the core including corestructures, fuel elements and control rods and material.
21 Understanding of reactor intrumentation and control system 22 Understanding of reactor safety system 23 Understanding of reactor cooling system 24 Understanding of reactor auxiliary system 25 Understanding of reactor water chemistry
Experimental Facility26 Understanding of functions and modes of operation of
experimental devices (In-core, ex-core, isotope production, beam tube, cold neutron source, neutron radiography facilities etc.).
27 Ability to implement the safety aspecs of experimental facility
Reactor Research Operation28 Understanding of facility operating characteristics during
steady state and transient conditions.29 Understanding of operational limits and conditions.30 Understanding of core management strategy and reactivity
control 31 Capability to operate facility e.g startup and shutdown from
various initial conditions and operation at power.32 Understanding of operation and maintenance requirements
and scheduling 33 Capability to perform the surveillance requirements of the
OLCs (instruments checks and calibration, control rodcalibration).
34 Understanding of procedures for normal and abnormaloperation and capability to apply them.
35 Understanding of emergency plans and procedures andcapability to apply them
High Medium Low N.A.Competency Level
36 Capability to perform fuel handling activities followingestablished procedures
37 Capability of handling and disposal of radioactive materialsand effluents following established procedures.
Q3: Regulation and Administration Rules and Regulation System
38 Comprehension of relevant national legislation that apply toresearch reactor facility.
39 Comprehension of relevant international legislation that apply to research reactor facility.
40 Comprehension of relevant codes and standards41 demonstrated ability to understand organizational norms and
expectations42 Understanding national regulatory bodies and their functions43 Comprehension of licenses and condition of license44 Understanding of staffing requirements for safe operation of the
facility
Quality Assurance45 Understanding of administrative procedures46 Understanding of administrative requirements of OLCs47 Understanding of facility access control procedures48
Understanding and capability of operational records retention
Q4: Personal and Interpersonal Effectiveness Decision Making
49 demonstrated ability to troubleshoot when problems occur andrefine choices to be presented
50 demonstrated ability to make trade-offs based on a full andrealistic assessment of the situation
51 demonstrated ability to analyse the risk and benefits of the bestalternatives
52 demonstrated ability to identify the causes of the most likelyproblems
Communication53 demonstrated ability to communicate complex or simple
messages with clarity and impact to widely varied forums, andprovide answers which reflect an awareness of the sensitivitiesand interests of the audience
54demonstrated ability to produce clear, concise, informedwritten reports which are appropriate to the needs of the reader
High Medium Low N.A.Competency Level
55 demonstrated ability to give timely and constructive feedbackwhen required
56 demonstrated ability to always explain the logic behind whythings should be done a certain way; where no logic prevails,investigates further to find rationale
Team Work57 demonstrated ability to build effective working relationships
with others at all levels, inside and outside the work unit58 demonstrated ability to actively contribute and participate in
meeting team objectives 59 demonstrated ability to be approachable and open to
suggestions from others60 demonstrated ability to review and evaluate outcomes against
those planned
Project Management61
demonstrated ability to set priorities and organises work tomeet established timeframes in accordance with requirements
62 demonstrated ability to adapt schedule and adjust priorities
Thank You
Attachment 8 Gap of Competency
Reactor Operation – Senior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.88 1.81 2.08 0.16 B2 Q1.1.2 Application of first aid. 1.92 0.08 B3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.92 -0.28 C4 Q1.1.4 Understanding of facility security procedures 2.00 0.06 B5 Q1.1.5 Understanding electricity and electronics techniques 1.46 0.13 B6 Q1.1.6 Ability to read and interpret technical drawings. 1.69 0.01 B7 Q1.1.7 Demonstrated ability to use modern computing systems. 1.38 0.38 B8 Q1.1.8 Ability to implement the safety culture 2.00 0.24 B9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 2.10 1.92 0.19 B
10 Q1.2.2 Understanding of radiation safety principles and procedures 2.38 -0.27 C11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 2.00 -0.06 C12 Q1.2.4 Understanding of radiation effects to human body 2.08 0.10 B13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 1.87 2.23 0.12 B14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 1.92 -0.04 C15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 1.46 0.07 B16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 1.75 2.15 0.08 B17 Q1.4.2 Capability to review the safety analysis report as required. 1.77 -0.12 C18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 1.23 0.18 B19 Q1.4.4 Understanding of nuclear emergency preparedness and response 1.85 -0.08 C20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 2.06 2.23 2.38 -0.09 C21 Q2.1.2 Understanding of reactor intrumentation and control system 2.00 -0.06 C22 Q2.1.3 Understanding of reactor safety system 2.38 -0.15 C23 Q2.1.4 Understanding of reactor cooling system 2.46 -0.40 C24 Q2.1.5 Understanding of reactor auxiliary system 2.38 -0.33 C25 Q2.1.6 Understanding of reactor water chemistry 1.77 -0.24 C26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 1.88 2.00 -0.12 C27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 1.77 0.23 B28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.2.07 1.92 0.31 B
29 Q2.3.2 Understanding of operational limits and conditions. 2.38 0.03 B30 Q2.3.3 Understanding of core management strategy and reactivity control 1.85 0.10 B31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.2.54 0.11 B
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 2.54 -0.36 C33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).2.46 -0.29 C
Competencies
Personnel Competency AvailableReactor Operation - Senior
No Level 1 Level 2 Level 3 Gap CriteriaCompetencies34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.2.38 -0.33 C
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 1.77 -0.06 C36 Q2.3.9 Capability to perform fuel handling activities following established procedures 1.62 -0.03 C37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.1.23 0.06 B
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 1.75 1.68 1.92 -0.28 C39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 1.54 -0.07 C40 Q3.1.3 Comprehension of relevant codes and standards 1.31 0.16 B41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 1.54 0.05 B42 Q3.1.5 Understanding national regulatory bodies and their functions 1.92 -0.10 C43 Q3.1.6 Comprehension of licenses and condition of license 1.85 -0.14 C44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 1.69 -0.05 C45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.83 1.77 -0.18 C46 Q3.2.2 Understanding of administrative requirements of OLCs 2.23 0.24 B47 Q3.2.3 Understanding of facility access control procedures 2.00 0.29 B48 Q3.2.4 Understanding and capability of operational records retention 1.31 0.46 B49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented1.85 1.81 1.92 0.31 B
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.77 0.29 B
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.77 0.29 B52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 1.77 0.47 B53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
1.94 1.92 0.19 B
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
2.00 0.12 B
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 1.85 0.21 B56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale2.00 0.12 B
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
1.92 1.92 0.31 B
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 1.92 0.25 B59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 2.08 -0.02 C60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 1.77 0.00 B61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 1.73 1.62 0.38 B
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 1.85 0.33 B
Reactor Operation - Senior
1.921.88 1.992.061.831.75
2.101.85
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.04
-0.07
0.070.25
-1.00
0.00
1.00
Gap
s
Reactor Operation - Senior
1.90 1.812.09 2.10
1.92 1.87 1.76 1.75
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.10-0.01 0.05 0.01
-1.00
0.00
1.00
Gap
s
Reactor Operation - Senior
2.022.23
1.94 1.882.02 2.07
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
-0.21
0.06
-0.05
-1.00
0.00
1.00
Gap
s
Reactor Operation - Senior
1.62 1.682.03
1.83
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
-0.06
0.20
-1.00
0.00
1.00
Gap
s
Reactor Operation - Senior
2.15
1.812.10
1.94 2.061.92
2.09
1.73
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
0.340.16 0.14
0.36
-1.00
0.00
1.00
Gap
s
Attachment 9 Gap of Competency
Reactor Operation – Junior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.49 1.50 1.77 0.06 B2 Q1.1.2 Application of first aid. 1.64 0.28 B3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.50 0.17 B4 Q1.1.4 Understanding of facility security procedures 1.55 -0.05 C5 Q1.1.5 Understanding electricity and electronics techniques 1.27 -0.02 C6 Q1.1.6 Ability to read and interpret technical drawings. 1.18 -0.10 C7 Q1.1.7 Demonstrated ability to use modern computing systems. 1.23 -0.23 C8 Q1.1.8 Ability to implement the safety culture 1.86 0.22 B9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 1.73 1.64 0.03 B
10 Q1.2.2 Understanding of radiation safety principles and procedures 1.91 -0.33 C11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 1.59 -0.26 C12 Q1.2.4 Understanding of radiation effects to human body 1.77 0.14 B13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 1.53 1.82 0.27 B14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 1.55 -0.13 C15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 1.23 0.11 B16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 1.22 1.59 0.33 B17 Q1.4.2 Capability to review the safety analysis report as required. 1.05 0.12 B18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 0.86 0.30 B19 Q1.4.4 Understanding of nuclear emergency preparedness and response 1.36 0.22 B20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 1.56 1.75 1.82 0.35 B21 Q2.1.2 Understanding of reactor intrumentation and control system 1.59 -0.01 C22 Q2.1.3 Understanding of reactor safety system 1.95 0.30 B23 Q2.1.4 Understanding of reactor cooling system 2.00 0.17 B24 Q2.1.5 Understanding of reactor auxiliary system 1.91 0.17 B25 Q2.1.6 Understanding of reactor water chemistry 1.23 0.02 B26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 1.30 1.27 0.06 B27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 1.32 0.52 A28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.1.64 1.68 0.32 B
29 Q2.3.2 Understanding of operational limits and conditions. 1.91 0.42 B30 Q2.3.3 Understanding of core management strategy and reactivity control 1.41 0.17 B31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.2.05 0.45 B
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 2.00 0.00 C33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).1.73 0.19 B
Competencies
Personnel Competency AvailableReactor Operation - Junior
No Level 1 Level 2 Level 3 Gap CriteriaCompetencies34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.1.77 0.23 B
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 1.36 0.05 B36 Q2.3.9 Capability to perform fuel handling activities following established procedures 1.36 -0.11 C37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.1.09 0.16 B
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 1.45 1.32 1.27 0.39 B39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 1.00 0.25 B40 Q3.1.3 Comprehension of relevant codes and standards 1.00 0.17 B41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 1.41 -0.08 C42 Q3.1.5 Understanding national regulatory bodies and their functions 1.64 0.11 B43 Q3.1.6 Comprehension of licenses and condition of license 1.55 -0.05 C44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 1.41 -0.08 C45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.57 1.41 0.26 B46 Q3.2.2 Understanding of administrative requirements of OLCs 1.73 0.61 A47 Q3.2.3 Understanding of facility access control procedures 1.77 0.06 B48 Q3.2.4 Understanding and capability of operational records retention 1.36 0.05 B49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented1.64 1.36 1.45 0.13 B
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.36 0.05 B
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.36 -0.03 C52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 1.27 0.14 B53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
1.59 1.64 0.20 B
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
1.68 0.32 B
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 1.36 0.30 B56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale1.68 -0.02 C
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
1.85 1.91 0.09 B
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 1.68 0.23 B59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 2.09 -0.01 C60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 1.73 -0.31 C61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 1.77 1.55 0.04 B
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 2.00 -0.33 C
Reactor Operation - Junior
1.561.491.78
1.56 1.621.45
1.681.64
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.070.21 0.17
0.03
-1.00
0.00
1.00
Gap
s
Reactor Operation - Junior
1.54 1.50 1.63 1.73 1.61 1.53 1.461.22
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.04
-0.10
0.080.24
-1.00
0.00
1.00
Gap
s
Reactor Operation - Junior
1.921.75
1.581.30
1.831.64
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
0.170.29
0.19
-1.00
0.00
1.00
Gap
s
Reactor Operation - Junior
1.43 1.32
1.811.57
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
0.100.24
-1.00
0.00
1.00
Gap
s
Reactor Operation - Junior
1.44 1.36
1.791.59
1.85 1.851.63
1.77
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
0.070.20
0.00
-0.15
-1.00
0.00
1.00
Gap
s
Attachment 10 Gap of Competency
Reactor Safety – Senior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.62 1.57 2.14 0.81 A2 Q1.1.2 Application of first aid. 1.67 1.15 A3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.52 1.25 A4 Q1.1.4 Understanding of facility security procedures 1.67 1.06 A5 Q1.1.5 Understanding electricity and electronics techniques 1.14 0.68 A6 Q1.1.6 Ability to read and interpret technical drawings. 0.90 0.78 A7 Q1.1.7 Demonstrated ability to use modern computing systems. 1.33 0.80 A8 Q1.1.8 Ability to implement the safety culture 2.14 0.77 A9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 2.13 1.81 0.74 A
10 Q1.2.2 Understanding of radiation safety principles and procedures 2.24 0.67 A11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 2.14 0.72 A12 Q1.2.4 Understanding of radiation effects to human body 2.33 0.62 A13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 1.32 1.52 0.75 A14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 1.29 0.71 A15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 1.14 0.90 A16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 1.46 1.86 1.10 A17 Q1.4.2 Capability to review the safety analysis report as required. 1.48 1.34 A18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 0.95 1.23 A19 Q1.4.4 Understanding of nuclear emergency preparedness and response 1.57 1.20 A20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 1.27 1.43 1.52 0.79 A21 Q2.1.2 Understanding of reactor intrumentation and control system 1.29 0.85 A22 Q2.1.3 Understanding of reactor safety system 1.67 0.92 A23 Q2.1.4 Understanding of reactor cooling system 1.67 0.47 B24 Q2.1.5 Understanding of reactor auxiliary system 1.14 0.99 A25 Q2.1.6 Understanding of reactor water chemistry 1.29 0.85 A26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 1.55 1.48 0.84 A27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 1.62 1.20 A28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.0.85 0.95 1.27 A
29 Q2.3.2 Understanding of operational limits and conditions. 1.05 1.32 A30 Q2.3.3 Understanding of core management strategy and reactivity control 0.86 1.37 A31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.0.52 1.25 A
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 0.71 1.33 A33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).0.62 1.24 A
Competencies
Personnel Competency AvailableReactor Safety - Senior
No Level 1 Level 2 Level 3 Gap CriteriaCompetencies34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.0.62 1.47 A
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 0.86 1.69 A36 Q2.3.9 Capability to perform fuel handling activities following established procedures 0.86 1.37 A37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.1.43 1.21 A
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 1.52 1.34 1.29 1.26 A39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 1.19 1.22 A40 Q3.1.3 Comprehension of relevant codes and standards 0.86 1.60 A41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 1.48 1.11 A42 Q3.1.5 Understanding national regulatory bodies and their functions 1.86 0.78 A43 Q3.1.6 Comprehension of licenses and condition of license 1.48 1.07 A44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 1.24 1.49 A45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.69 1.71 0.88 A46 Q3.2.2 Understanding of administrative requirements of OLCs 1.38 1.21 A47 Q3.2.3 Understanding of facility access control procedures 1.90 0.78 A48 Q3.2.4 Understanding and capability of operational records retention 1.76 0.74 A49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented1.90 1.81 1.90 0.91 A
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.81 0.96 A
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.76 1.10 A52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 1.76 1.06 A53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
2.04 2.10 0.59 A
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
2.10 0.54 A
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 1.90 0.64 A56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale2.05 0.82 A
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
2.01 2.00 0.64 A
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 1.95 0.64 A59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 2.05 0.68 A60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 2.05 0.63 A61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 1.76 1.76 0.83 A
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 1.76 0.87 A
Reactor Safety - Senior
2.52
1.62
2.34
1.27
2.57
1.52
2.69
1.90
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.901.06 1.06
0.79
-1.00
0.00
1.00
2.00
Gap
s
Reactor Safety - Senior
2.48
1.57
2.82
2.13 2.11
1.32
2.68
1.46
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.910.69 0.79
1.22
-1.00
0.00
1.00
2.00
Gap
s
Reactor Safety - Senior
2.24
1.43
2.57
1.55
2.20
0.85
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
0.811.02
1.35
-1.00
0.00
1.00
2.00
Gap
s
Reactor Safety - Senior
2.56
1.34
2.59
1.69
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
1.22
0.90
-1.00
0.00
1.00
2.00
Gap
s
Reactor Safety - Senior
2.82
1.81
2.68
2.04
2.66
2.01
2.61
1.76
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
1.01
0.65 0.650.85
-1.00
0.00
1.00
2.00
Gap
s
Attachment 11 Gap of Competency
Reactor Safety – Junior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.24 1.42 1.92 0.23 B2 Q1.1.2 Application of first aid. 1.83 0.26 B3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.58 0.65 A4 Q1.1.4 Understanding of facility security procedures 1.42 0.58 A5 Q1.1.5 Understanding electricity and electronics techniques 1.00 0.52 A6 Q1.1.6 Ability to read and interpret technical drawings. 0.75 0.54 A7 Q1.1.7 Demonstrated ability to use modern computing systems. 1.08 0.30 B8 Q1.1.8 Ability to implement the safety culture 1.75 0.49 B9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 1.65 1.42 0.39 B
10 Q1.2.2 Understanding of radiation safety principles and procedures 1.83 0.26 B11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 1.58 0.46 B12 Q1.2.4 Understanding of radiation effects to human body 1.75 0.49 B13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 0.89 1.08 0.54 A14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 0.92 0.42 B15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 0.67 0.67 A16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 1.00 1.33 0.95 A17 Q1.4.2 Capability to review the safety analysis report as required. 0.83 0.83 A18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 0.67 0.81 A19 Q1.4.4 Understanding of nuclear emergency preparedness and response 1.17 0.88 A20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 0.73 0.83 0.75 0.92 A21 Q2.1.2 Understanding of reactor intrumentation and control system 0.58 0.89 A22 Q2.1.3 Understanding of reactor safety system 1.33 0.52 A23 Q2.1.4 Understanding of reactor cooling system 1.00 0.62 A24 Q2.1.5 Understanding of reactor auxiliary system 0.50 1.02 A25 Q2.1.6 Understanding of reactor water chemistry 0.83 0.74 A26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 0.88 0.75 0.87 A27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 1.00 1.05 A28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.0.48 0.33 1.19 A
29 Q2.3.2 Understanding of operational limits and conditions. 0.50 1.12 A30 Q2.3.3 Understanding of core management strategy and reactivity control 0.25 1.08 A31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.0.33 0.90 A
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 0.50 0.93 A33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).0.17 1.21 A
Jenis Kompetensi
Personnel Competency AvailableReactor Safety - Junior
No Level 1 Level 2 Level 3 Gap CriteriaJenis Kompetensi34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.0.25 1.18 A
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 0.42 1.35 A36 Q2.3.9 Capability to perform fuel handling activities following established procedures 0.33 1.19 A37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.1.67 0.14 B
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 1.02 0.80 0.67 1.00 A39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 0.42 1.06 A40 Q3.1.3 Comprehension of relevant codes and standards 0.33 1.14 A41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 1.00 0.71 A42 Q3.1.5 Understanding national regulatory bodies and their functions 1.42 0.39 B43 Q3.1.6 Comprehension of licenses and condition of license 0.92 0.70 A44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 0.83 0.88 A45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.25 1.00 0.71 A46 Q3.2.2 Understanding of administrative requirements of OLCs 0.75 1.06 A47 Q3.2.3 Understanding of facility access control procedures 1.67 0.19 B48 Q3.2.4 Understanding and capability of operational records retention 1.58 0.27 B49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented1.78 1.60 1.50 0.45 B
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.58 0.27 B
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.58 0.37 B52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 1.75 0.15 B53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
1.73 1.67 0.33 B
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
1.92 -0.01 C
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 1.58 0.46 B56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale1.75 0.25 B
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
1.94 1.92 0.27 B
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 1.92 0.13 B59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 2.00 0.14 B60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 1.92 -0.01 C61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 1.83 1.75 0.06 B
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 1.92 -0.11 C
Reactor Safety - Junior
1.80
1.24
1.65
0.73
1.72
1.02
1.951.78
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.56
0.92
0.70
0.17
-1.00
0.00
1.00
Gap
s
Reactor Safety - Junior
1.86
1.42
2.05
1.651.43
0.89
1.87
1.00
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.45 0.400.54
0.87
-1.00
0.00
1.00
Gap
s
Reactor Safety - Junior
1.62
0.83
1.83
0.88
1.50
0.48
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
0.790.96 1.03
-1.00
0.00
1.00
2.00
Gap
s
Reactor Safety - Junior
1.64
0.80
1.81
1.25
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
0.84
0.56
-1.00
0.00
1.00
Gap
s
Reactor Safety - Junior
1.921.60
1.991.73
2.071.94 1.81 1.83
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
0.31 0.260.13
-0.02
-1.00
0.00
1.00
Gap
s
Attachment 12 Gap of Competency
Reactor Maintenance – Senior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.92 2.03 2.14 0.59 A2 Q1.1.2 Application of first aid. 1.86 0.41 B3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.71 0.42 B4 Q1.1.4 Understanding of facility security procedures 1.93 0.34 B5 Q1.1.5 Understanding electricity and electronics techniques 2.50 0.03 B6 Q1.1.6 Ability to read and interpret technical drawings. 1.93 0.54 A7 Q1.1.7 Demonstrated ability to use modern computing systems. 2.07 0.53 A8 Q1.1.8 Ability to implement the safety culture 2.07 0.53 A9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 2.07 1.93 0.34 B
10 Q1.2.2 Understanding of radiation safety principles and procedures 2.14 0.39 B11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 2.00 0.40 B12 Q1.2.4 Understanding of radiation effects to human body 2.21 0.25 B13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 1.90 2.21 0.12 B14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 2.00 0.20 B15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 1.50 0.70 A16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 1.70 2.14 0.39 B17 Q1.4.2 Capability to review the safety analysis report as required. 1.71 0.35 B18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 1.36 0.51 A19 Q1.4.4 Understanding of nuclear emergency preparedness and response 1.57 0.63 A20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 1.78 2.02 2.14 0.26 B21 Q2.1.2 Understanding of reactor intrumentation and control system 2.14 0.72 A22 Q2.1.3 Understanding of reactor safety system 2.29 0.45 B23 Q2.1.4 Understanding of reactor cooling system 2.36 0.31 B24 Q2.1.5 Understanding of reactor auxiliary system 1.93 0.60 A25 Q2.1.6 Understanding of reactor water chemistry 1.29 0.78 A26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 1.96 2.00 0.73 A27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 1.93 0.80 A28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.1.36 1.86 0.28 B
29 Q2.3.2 Understanding of operational limits and conditions. 1.86 0.48 B30 Q2.3.3 Understanding of core management strategy and reactivity control 1.57 0.36 B31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.1.14 0.99 A
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 1.64 1.02 A33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).1.14 1.52 A
Competencies
Personnel Competency AvailableReactor Maintenance - Senior
No Level 1 Level 2 Level 3 Gap CriteriaCompetencies34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.1.07 1.26 A
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 1.21 0.92 A36 Q2.3.9 Capability to perform fuel handling activities following established procedures 1.14 0.59 A37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.1.00 0.73 A
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 1.68 1.54 1.57 0.56 A39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 1.50 0.50 A40 Q3.1.3 Comprehension of relevant codes and standards 1.29 0.78 A41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 1.50 0.57 A42 Q3.1.5 Understanding national regulatory bodies and their functions 1.93 0.14 B43 Q3.1.6 Comprehension of licenses and condition of license 1.64 0.29 B44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 1.36 0.51 A45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.82 1.71 0.62 A46 Q3.2.2 Understanding of administrative requirements of OLCs 1.79 0.68 A47 Q3.2.3 Understanding of facility access control procedures 1.86 0.28 B48 Q3.2.4 Understanding and capability of operational records retention 1.93 0.60 A49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented2.20 1.98 2.14 0.52 A
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.79 0.81 A
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.93 0.60 A52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 2.07 0.60 A53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
2.30 2.21 0.45 B
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
2.29 0.45 B
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 2.36 0.31 B56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale2.36 0.24 B
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
2.38 2.50 0.17 B
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 2.36 0.31 B59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 2.43 0.24 B60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 2.21 0.52 A61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 2.14 2.14 0.39 B
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 2.14 0.46 B
Reactor Maintenance - Senior
2.32
1.92
2.49
1.78
2.19
1.68
2.63
2.20
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.39
0.700.51 0.43
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Senior
2.45
2.03
2.422.07
2.241.90
2.17
1.70
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.420.35 0.34
0.47
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Senior
2.54
2.02
2.73
1.962.18
1.36
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
0.52
0.77 0.82
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Senior
2.02
1.54
2.37
1.82
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
0.48 0.55
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Senior
2.62
1.98
2.67
2.30
2.682.38
2.57
2.14
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
0.63
0.36 0.310.42
-1.00
0.00
1.00
Gap
s
Attachment 13 Gap of Competency
Reactor Maintenance – Junior
No Level 1 Level 2 Level 3 Gap Criteria1 Q1 Q1.1 Q1.1.1 Understanding of industrial safety procedures at work. 1.04 1.47 1.61 0.31 B2 Q1.1.2 Application of first aid. 1.56 0.11 B3 Q1.1.3 Understanding and application of plant fire protection plan and fire drills 1.50 0.08 B4 Q1.1.4 Understanding of facility security procedures 1.33 0.25 B5 Q1.1.5 Understanding electricity and electronics techniques 1.72 0.44 B6 Q1.1.6 Ability to read and interpret technical drawings. 1.22 0.61 A7 Q1.1.7 Demonstrated ability to use modern computing systems. 1.17 0.58 A8 Q1.1.8 Ability to implement the safety culture 1.67 0.33 B9 Q1.2 Q1.2.1 Understanding of fundamentals of nuclear physics 1.25 0.89 0.53 A
10 Q1.2.2 Understanding of radiation safety principles and procedures 1.50 0.33 B11 Q1.2.3 Comprehension of radiation monitoring methods and survey equipment and their use. 1.00 0.67 A12 Q1.2.4 Understanding of radiation effects to human body 1.61 0.31 B13 Q1.3 Q1.3.1 Understanding of fundamentals of reactor theory 0.61 0.89 0.61 A14 Q1.3.2 Comprehension of heat transfer, thermodynamic and fluid mechanics 0.50 0.83 A15 Q1.3.3 Understanding of materials and their behaviour in radiation field and their aging. 0.44 0.81 A16 Q1.4 Q1.4.1 Understanding of nuclear safety principles 0.83 1.00 0.75 A17 Q1.4.2 Capability to review the safety analysis report as required. 0.67 0.50 A18 Q1.4.3 Understanding and demonstrated ability of nuclear material accountability 0.72 0.28 B19 Q1.4.4 Understanding of nuclear emergency preparedness and response 0.94 0.47 B20 Q2 Q2.1 Q2.1.1 Understanding of general features of the core 0.76 0.86 0.83 0.75 A21 Q2.1.2 Understanding of reactor intrumentation and control system 0.94 0.97 A22 Q2.1.3 Understanding of reactor safety system 1.06 0.86 A23 Q2.1.4 Understanding of reactor cooling system 1.11 0.64 A24 Q2.1.5 Understanding of reactor auxiliary system 0.72 0.86 A25 Q2.1.6 Understanding of reactor water chemistry 0.50 0.83 A26 Q2.2 Q2.2.1 Understanding of functions and modes of operation of experimental devices 0.92 0.89 1.11 A27 Q2.2.2 Ability to implement the safety aspecs of experimental facility 0.94 0.89 A28 Q2.3 Q2.3.1 Understanding of facility operating characteristics during steady state and transient
conditions.0.52 0.39 0.78 A
29 Q2.3.2 Understanding of operational limits and conditions. 0.61 1.06 A30 Q2.3.3 Understanding of core management strategy and reactivity control 0.50 0.67 A31 Q2.3.4 Capability to operate facility e.g startup and shutdown from various initial conditions and
operation.0.44 0.72 A
32 Q2.3.5 Understanding of operation and maintenance requirements and scheduling 0.61 0.72 A33 Q2.3.6 Capability to perform the surveillance requirements of the OLCs (instruments checks and
calibration, control rod calibration).0.50 1.08 A
Competencies
Personnel Competency AvailableReactor Maintenance - Junior
No Level 1 Level 2 Level 3 Gap CriteriaCompetencies34 Q2.3.7 Understanding of procedures for normal and abnormal operation and capability to apply
them.0.56 0.69 A
35 Q2.3.8 Understanding of emergency plans and procedures and capability to apply them 0.33 0.92 A36 Q2.3.9 Capability to perform fuel handling activities following established procedures 0.67 0.42 B37 Q2.3.10 Capability of handling and disposal of radioactive materials and effluents following
established procedures.0.56 0.61 A
38 Q3 Q3.1 Q3.1.1 Comprehension of relevant national legislation that apply to research reactor facility. 0.81 0.55 0.50 1.00 A39 Q3.1.2 Comprehension of relevant international legislation that apply to research reactor facility. 0.44 0.89 A40 Q3.1.3 Comprehension of relevant codes and standards 0.28 0.97 A41 Q3.1.4 demonstrated ability to understand organizational norms and expectations 0.61 0.89 A42 Q3.1.5 Understanding national regulatory bodies and their functions 1.06 0.44 B43 Q3.1.6 Comprehension of licenses and condition of license 0.56 0.86 A44 Q3.1.7 Understanding of staffing requirements for safe operation of the facility 0.39 0.94 A45 Q3.2 Q3.2.1 Understanding of administrative procedures 1.07 1.00 0.42 B46 Q3.2.2 Understanding of administrative requirements of OLCs 0.61 1.14 A47 Q3.2.3 Understanding of facility access control procedures 1.22 0.44 B48 Q3.2.4 Understanding and capability of operational records retention 1.44 0.39 B49 Q4 Q4.1 Q4.1.1 demonstrated ability to troubleshoot when problems occur and refine choices to be
presented1.45 1.17 1.11 0.72 A
50 Q4.1.2 demonstrated ability to make trade-offs based on a full and realistic assessment of situation
1.17 0.33 B
51 Q4.1.3 demonstrated ability to analyse the risk and benefits of the best alternatives 1.17 0.33 B52 Q4.1.4 demonstrated ability to identify the causes of the most likely problems 1.22 0.53 A53 Q4.3 Q4.2.1 demonstrated ability to communicate complex or simple messages with clarity and impact
to widely varied forums, and provide answers which reflect an awareness of the sensitivities and interests of the audience
1.40 1.39 0.53 A
54 Q4.2.2 demonstrated ability to produce clear, concise, informed written reports which are appropriate to the needs of the reader
1.44 0.47 B
55 Q4.2.3 demonstrated ability to give timely and constructive feedback when required 1.28 0.72 A56 Q4.2.4 demonstrated ability to always explain the logic behind why things should be done a
certain way; where no logic prevails, investigates further to find rationale1.50 0.58 A
57 Q4.4 Q4.3.1 demonstrated ability to build effective working relationships with others at all levels, inside and outside the work unit
1.76 1.78 0.14 B
58 Q4.3.2 demonstrated ability to actively contribute and participate in meeting team objectives 1.72 0.28 B59 Q4.3.3 demonstrated ability to be approachable and open to suggestions from others 1.89 0.44 B60 Q4.3.4 demonstrated ability to review and evaluate outcomes against those planned 1.67 0.33 B61 Q4.5 Q4.4.1 demonstrated ability to set priorities and organises work to meet established timeframes in
accordance with requirements 1.47 1.44 0.39 B
62 Q4.4.2 demonstrated ability to adapt schedule and adjust priorities 1.50 0.50 A
Reactor Maintenance - Junior
1.55
1.04
1.63
0.76
1.54
0.81
1.90
1.45
0.00
1.00
2.00
3.00
Basic TechnicalCompetency
SpecificCompetency on
Research Reactor
Regulation andAdministration
Personal andInterpersonalEffectiveness
Category Level I
IdealFactual
0.51
0.860.73
0.45
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Junior
1.811.47
1.71
1.25 1.36
0.61
1.33
0.83
0.00
1.00
2.00
3.00
General knowledge Basic of radiation Basic concept of nuclearreactor
Basic of nuclear safety
Quadrant 1: Basic Technical Competency
0.340.46
0.75
0.50
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Junior
1.68
0.86
1.92
0.92
1.28
0.52
0.00
1.00
2.00
3.00
Research reactor technology Reactor experimental facility Operation of research reactor
Quadrant 2: Specific Competency on Research Reactor
0.821.00
0.77
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Junior
1.40
0.55
1.67
1.07
0.00
1.00
2.00
3.00
Regulation system Quality management
Quadrant 3: Regulation and Administration
0.86
0.60
-1.00
0.00
1.00
Gap
s
Reactor Maintenance - Junior
1.65
1.17
1.98
1.40
2.061.76
1.92
1.47
0.00
1.00
2.00
3.00
Decision-making Communication Team work Project management
Quadrant 4: Personal and Interpersonal Effectiveness
0.480.58
0.300.44
-1.00
0.00
1.00
Gap
s
Attachment 14Training Module related to Specific Competency
Title SubjectPengetahuan Dasar Umum
1 Kemampuan menerapkan prosedur keselamatan dan kesehatan kerja
K-3 untuk PetugasPencegahan, Penanggulangan dan Rehabilitas
2 Kemampuan melakukan pertolongan pertama pada kecelakaan 1. K-3 untuk Pekerja; 2. K-3 untuk Petugas
P3K
3 Kemampuan menerapkan prosedur penanggulangan bahaya kebakaran
Proteksi Radiasi & K-3 untuk SATPAM
Pemadam Kebakaran
4 Pengertian terhadap prosedur keamanan (security) fasilitas 1. Diklat pengamanan 2. Diklat SATPAM
5 Pengertian terhadap teknik listrik dan elektronika Maintenance of Research Reactor
Electric Power Technique
6 Pengertian terhadap teknik sipil dan mekanik Maintenance of RR Basic of Electromechanic Reactor
7 Pengertian terhadap sistem berbasis komputer Instrumentasi & Kendali Reaktor Nuklir
Sistem Informasi Proses
8 Kemampuan menerapkan budaya keselamatan Safety in Operation & Utilization of RR
Safety Culture of RR
Pengetahuan Dasar Radiasi9 Pengertian terhadap fisika inti / radiasi Diklat PR Fisika Radiasi
10 Pengertian terhadap prinsip proteksi radiasi Diklat PR Dasar PR
11 Pengertian terhadap metode monitoring dan survai radiasi Diklat PR Dasar Pengukuran
12 Pengertian terhadap bahaya radiasi terhadap manusia Diklat PR Bahaya Radiasi
Pengetahuan Dasar Reaktor13 Pengertian terhadap teori reaktor Penyegaran / Operator &
Supervisor ReaktorDasar Teori Reaktor
14 Pengertian terhadap teori perpindahan panas, termodinamika, dan mekanika fluida
Penyegaran / Operator & Supervisor Reaktor
Perpindahan Panas
15 Pengertian terhadap ilmu bahan (material), karakteristiknya di medan radiasi dan sifat penuaan (aging) nya
1. Pengantar Teknologi Reaktor Daya; 2. Safety in Operation & Utilization of RR; 3. NTC on Aging Management for RR
1. Bahan Reaktor dan Efek Radiasinya; 2. Reactor Aging; 3. Metodhology of Ageing Management (Mechanical & Non Machanical)
Keselamatan Nuklir16 Pengertian terhadap prinsip keselamatan nuklir National Basic Professional TC
on Nuclear SafetyBasic Principle of Nuclear Safety
17 Kemampuan melakukan review Laporan Analisis Keselamatan (LAK) Operator & Supervvisor Reaktor GA Siwabessy
Analisis Keselamatan Reaktor GA Siwabessy
18 Penerapan sistem akutansi bahan nuklir SSAC Statistik Akutansi Bahan Nuklir
19 Pengertian terhadap kesiapsiagaan nuklir 1. Batan-IAEA NTC on Operation & Maintenance of RR; 2. National Basic Prof. TC on NS
Introduction to Emergency Planning & Preparedness; . 2. Emergency Preparadness & Response
Teknologi Reaktor Riset20 Pengertian terhadap teras reaktor Penyegaran Operator &
Supervisor Reaktor SerpongPenanganan Teras RSG
21 Pengertian terhadap sistem instrumentasi dan kendali reaktor 1. Maintenance of Research Reactor; 2. Operator & Supervisor Reaktor GA Siwabessy
Basic of Instrumentation & Control; 2. SIK
22 Pengertian terhadap sistem keselamatan reaktor Supervisor Reaktor Triga Keselamatan Reaktor
23 Pengertian terhadap sistem pendingin reaktor Penyegaran Operator & Supervisor Reaktor Serpong
Sistem Pendingin Reaktor
Training CourseSpecific Competency
Title SubjectTraining CourseSpecific Competency
24 Pengertian terhadap sistem bantu (auxiliary system) Penyegaran Operator & Supervisor Reaktor Serpong
Sistem Bantu
25 Pengertian terhadap kimia air (water chemistry) reaktor NTC on Water Chemistry of Nuclear Reactor System
Water Chemistry of Indonesia Research Reactor
Fasilitas Eksperimen26 Pengertian terhadap fungsi, mode pengoperasian dan prinsip kerja
peralatan eksperimen1. Operator Reaktor GA Siwabessy; 2. Perawatan Sistem penunjang/ Bantu Reaktor
2. Fasilitas Iradiasi
27Kemampuan menerapkan aspek keselamatan fasilitas eksperimen
National Basic Professional TC on Nuclear Safety
Code of Conduct on the Safety of RR
Pengoperasian Reaktor Riset28 Pengertian terhadap karakteristika operasi dalam kondisi "steady
state" dan transien. Aspek Neutronik & Termohidrolika PLTN
1.Komputasi Neutronik: Reaktor Kondisi Tunak & Tak-Tunak; 2. Komputasi Thermohidrolika: Sistem Reaktor Kondisi Tak-Tunak
29 Pengertian terhadap batas kondisi operasi reaktor National Workshop on Reactor Calculation for Burn-up calculation …
Some Operating Limits and Condition of RR
30 Pengertian terhadap strategi manajemen teras dan pengendalian reaktivitas
1. Manajemen Teras RSG GAS;
1. Teori Manajemen Teras; 2. Reaktivitas Batang Kendali
31 Pengoperasian reaktor: menghidupkan (start up), mengubah daya, dan mematikan (shut down)
Instrumentasi & Kendali Reaktor Nuklir
1. Teknik Pengukuran Daya Reaktor; 2. Teknik Kendali Daya
32 Pengertian terhadap persyaratan dan jadwal operasi serta perawatan 1. Penyegaran Oprtr & Suprv RSG; 2. maintenance of RR
1. Manajemen Operasi reaktor; 2. Management of Maintanance
33 Kemampuan menerapkan pengecekan dan kalibrasi instrumen serta kalibrasi batang kendali dan daya (Persiapan Sarana Operasi - PSO)
Instrumentasi & Kendali Reaktor Nuklir;
Praktek Kalibrasi Alat Ukur, Daya Reaktor, dan Batang Kendali
34 Kemampuan menerapkan prosedur operasi normal dan abnormal Operator dan Supervisor Reaktor GA Siwabssy
1. Teknik Operasi Reaktor; 2. Prosedur Pengendalian reaktor pd Kondisi Abnormal
35 Kemampuan menerapkan "emergency planning" Kualifikasi & Rekualifikasi Operator & Supervisor Triga
Penanganan Keadaan darurat
36 Kemampuan mengelola bahan bakar sesuai prosedur Supervisor Reaktor TrigaPraktikum Penanganan Bahan Bakar
37 Kemampuan mengelola limbah radioaktif sesuai prosedur Kualifikasi & Rekualifikasi Operator & Supervisor Triga
Pengelolaan Limbah RA
Ketentuan dan Sistem Regulasi38 Pengertian terhadap ketentuan nasional yang terkait dengan reaktor
riset.Operator & Supervisor Reaktor Peraturan Bidang Nuklir
39 Pengertian terhadap ketentuan internasional yang terkait dengan reaktor riset.
National Training Course on the ISI of Research Reactor
Code Requirement for ISI of Research Reactor
40 Pengertian terhadap "code and standard" yang berkaitan dengan reaktor riset
1. Basic Prof TC on NS; 2. National Training Course on the ISI of Research Reactor
1. Code of Conduct on the Safety RR; 2. Code of Conduct on Safety of RR & Safety Requirement for RR
41 Pengertian terhadap norma dan tuntutan organisasi Belum Ketemu Belum Ketemu
42 Pengertian terhadap fungsi dan tugas BAPETEN Penyegaran Operator & Supervisor Reaktor
Regulasi & Perizinan
43 Pengertian terhadap sistem lisensi dan ketentuannya Penyegaran Operator & Supervisor Reaktor
Regulasi & Perizinan
44 Pengertian terhadap persyaratan (jumlah dan kualifikasi) personil untuk keselamatan operasi fasilitas
Safety in Operation & Utilization of R R
Recruitment, Qualification, & Training of Personnel
Jaminan Kualitas45 Pengertian terhadap prosedur administrasi Pengendalian & Pencatatan
DokumenProsedur
46 Pengertian terhadap Batas Kondisi Operasi Batan IAEA NTC on Operation & Maintenance of RR
Operation Limits & Conditioning
Title SubjectTraining CourseSpecific Competency
47 Pengertian terhadap prosedur pengendalian "keluar-masuk personil" ke / dari fasilitas
Operator & Supervisor Reaktor
Proteksi Fisik & Access Control
48 Pengertian terhadap pemeliharaan dokumen/rekaman 1. Pembuatan Manual Sistem Jaminan Mutu; 2. Pengendalian & Pencatatan Dokumen
Dasar-dasar Sistem Mutu ISO 9001:2000; 2. Pengendalian Dokumen
Pengambilan Keputusan49 Kemampuan mengambil tindakan penanggulangan masalah Fungsional Peneliti; Manajemen
II, Manajemen Praktis IITeknik Penyelesaian Masalah; Teknik Penyelesaian Masalah , Penyel. Masalah
50 Kemampuan mengambil keputusan dilematik berdasarkan analisis situasi yang realistik
Adum, Manajemen Praktis, Spama/Spamen
Pengambilan Keputusan, Manajemen Penyelesaian Konflik
51 Kemampuan melakukan analisis risiko dan keuntungan terhadap alternatif terbaik.
Adum, Pembinaan Pejabat Esl. III
Pengambilan Keputusan, Penyel. Mslh dan PK
52 Kemampuan mengidentifikasi kemungkinan penyebab masalah Pembinaan Pejabat Esel. III Penyelesaian Masalah & Pengambilan Keputusan
Komunikasi53 Kemampuan berkomunikasi lisan dihadapan forum terbuka Teknik Presentasi, TOT Teknik Presentasi
54 Kemampuan berkomunikasi secara tertulis Teknik penulisan Laporan Ilmiah
55 Kemampuan menyampaikan umpan balik yang konstruktif Spama/Spamen Telaahan Staf
56 Kemampuan menjelaskan latar belakang suatu tugas yang harus diselesaikan secara logis
Spama/Spamen
Kerjasama Tim57 Kemampuan membangun hubungan kerja yang efektif dengan
semua pihakAdum/ Spama/Spamen Tim Building
58 Kemampuan berpartisipasi aktif dalam pertemuan kelompok59 Kemampuan menerima saran dan kritik dari pihak lain Dinamika Kelompok Penerimaan Diri
60 Kemampuan melakukan evaluasi hasil dan rencana
Manajemen Proyek61 Kemampuan menentukan prioritas dan mengorganisasi pekerjaan Manajemen Proyek PMBI,
Manajemen PraktisPerencanaan Proyek, Manajemen Proyek & Permslhannya
62 Kemampuan menyesuaikan jadwal dan prioritas Manajemen III Manajemen Proyek & Network Planning