tnat riga

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.



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


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


Staff


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



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.



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.



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.



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.


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;



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



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).



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


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



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.



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



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.



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.



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.



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



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.



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



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.



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


6 Sudijono, ST.Center for Development of Research Reactor


7 Dr. M. Dhandhang PurwadiCenter for Development of Research Reactor


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


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


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


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


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


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


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


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



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


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


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


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


1.59 1.64 0.20 B


1.68 0.32 B


certain way; where no logic prevails, investigates further to find rationale1.68 -0.02 C


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


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



Research Reactor



Category Level I

IdealFactual

0.070.21 0.17

0.03

-1.00

0.00

1.00

Gap

s


1.54 1.50 1.63 1.73 1.61 1.53 1.461.22

0.00

1.00

2.00

3.00




0.04

-0.10

0.080.24

-1.00

0.00

1.00

Gap

s


1.921.75

1.581.30

1.831.64

0.00

1.00

2.00

3.00



0.170.29

0.19

-1.00

0.00

1.00

Gap

s


1.43 1.32

1.811.57

0.00

1.00

2.00

3.00



0.100.24

-1.00

0.00

1.00

Gap

s


1.44 1.36

1.791.59

1.85 1.851.63

1.77

0.00

1.00

2.00

3.00



0.070.20

0.00

-0.15

-1.00

0.00

1.00

Gap

s


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


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


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


2.04 2.10 0.59 A


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


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



Research Reactor



Category Level I

IdealFactual

0.901.06 1.06

0.79

-1.00

0.00

1.00

2.00

Gap

s


2.48

1.57

2.82

2.13 2.11

1.32

2.68

1.46

0.00

1.00

2.00

3.00




0.910.69 0.79

1.22

-1.00

0.00

1.00

2.00

Gap

s


2.24

1.43

2.57

1.55

2.20

0.85

0.00

1.00

2.00

3.00



0.811.02

1.35

-1.00

0.00

1.00

2.00

Gap

s


2.56

1.34

2.59

1.69

0.00

1.00

2.00

3.00



1.22

0.90

-1.00

0.00

1.00

2.00

Gap

s


2.82

1.81

2.68

2.04

2.66

2.01

2.61

1.76

0.00

1.00

2.00

3.00



1.01

0.65 0.650.85

-1.00

0.00

1.00

2.00

Gap

s


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






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



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


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


1.73 1.67 0.33 B


1.92 -0.01 C




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


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



Research Reactor



Category Level I

IdealFactual

0.56

0.92

0.70

0.17

-1.00

0.00

1.00

Gap

s


1.86

1.42

2.05

1.651.43

0.89

1.87

1.00

0.00

1.00

2.00

3.00




0.45 0.400.54

0.87

-1.00

0.00

1.00

Gap

s


1.62

0.83

1.83

0.88

1.50

0.48

0.00

1.00

2.00

3.00



0.790.96 1.03

-1.00

0.00

1.00

2.00

Gap

s


1.64

0.80

1.81

1.25

0.00

1.00

2.00

3.00



0.84

0.56

-1.00

0.00

1.00

Gap

s


1.921.60

1.991.73

2.071.94 1.81 1.83

0.00

1.00

2.00

3.00



0.31 0.260.13

-0.02

-1.00

0.00

1.00

Gap

s


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






Competencies

Personnel Competency AvailableReactor Maintenance - Senior


them.1.07 1.26 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


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


2.30 2.21 0.45 B


2.29 0.45 B




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


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



Research Reactor



Category Level I

IdealFactual

0.39

0.700.51 0.43

-1.00

0.00

1.00

Gap

s


2.45

2.03

2.422.07

2.241.90

2.17

1.70

0.00

1.00

2.00

3.00




0.420.35 0.34

0.47

-1.00

0.00

1.00

Gap

s


2.54

2.02

2.73

1.962.18

1.36

0.00

1.00

2.00

3.00



0.52

0.77 0.82

-1.00

0.00

1.00

Gap

s


2.02

1.54

2.37

1.82

0.00

1.00

2.00

3.00



0.48 0.55

-1.00

0.00

1.00

Gap

s


2.62

1.98

2.67

2.30

2.682.38

2.57

2.14

0.00

1.00

2.00

3.00



0.63

0.36 0.310.42

-1.00

0.00

1.00

Gap

s


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






Competencies

Personnel Competency AvailableReactor Maintenance - Junior


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


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


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


1.40 1.39 0.53 A


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


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


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



Research Reactor



Category Level I

IdealFactual

0.51

0.860.73

0.45

-1.00

0.00

1.00

Gap

s


1.811.47

1.71

1.25 1.36

0.61

1.33

0.83

0.00

1.00

2.00

3.00




0.340.46

0.75

0.50

-1.00

0.00

1.00

Gap

s


1.68

0.86

1.92

0.92

1.28

0.52

0.00

1.00

2.00

3.00



0.821.00

0.77

-1.00

0.00

1.00

Gap

s


1.40

0.55

1.67

1.07

0.00

1.00

2.00

3.00



0.86

0.60

-1.00

0.00

1.00

Gap

s


1.65

1.17

1.98

1.40

2.061.76

1.92

1.47

0.00

1.00

2.00

3.00



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

tnat riga

Documents

training course

annual training program

training review team

training review service

nuclear safety

iaea education

nuclear technology research

research reactor personnel