Analisis Kejadian pada Sistem Pendingin Primer Reaktor Menggunakan Functional Modeling

Selama waktu operasi reaktor, struktur, sistem dan komponen (SSK) reaktor, misalnya sistem pendingin primer, akan mengalami penuaan atau keusangan yang akan mempengaruhi kinerja dan operasi selamat dari reaktor tersebut. Hal ini juga berlaku pada Reaktor Serba Guna G.A. Siwabessy (RSG-GAS) yang usianya lebih dari 30 tahun. Oleh karena itu program manajemen penuaan harus dilakukan untuk mengatasi hal tersebut. Salah satu aktivitas yang dilakukan adalah dengan melakukan penapisan komponen kritis sistem pendingin primer. Penelitian ini bertujuan untuk melakukan penapisan tersebut menggunakan model multilevel flow modeling (MFM) pada sistem pendingin primer RSG-GAS. MFM adalah salah satu metode functional modeling yang mengubah sistem kompleks menjadi struktur fungsi-fungsi yang saling terhubung dengan hubungan sebab akibat. Metode yang dilakukan adalan dengan menerapkan beberapa skenario kejadian kecelakaan loss of flow accident (LOFA) yang terdapat pada Laporan Analisis Keselamatan (LAK) RSG-GAS pada model MFM tersebut. Dampak dari kejadian tersebut dapat dianalisis menggunakan aturan jalur perambatan (influence propagation). Hasil investigasi berupa komponen-komponen yang terdampak, yaitu katup isolasi, pompa primer dan alat penukar panas, dikelompokkan sebagai komponen kritis dan harus mendapat perhatian untuk penanganan lebih lanjut. Jika komponen-komponen tersebut mengalami keusangan atau kerusakan maka harus dilakukan perawatan atau penggantian sehingga kinerja reaktor dapat dipertahankan dan reaktor dapat tetap beroperasi dengan aman dan selamat.

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Functional Information of System Components Influenced by Operators’ Actions on Emergency Operating Procedure

Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors ◽

10.1115/icone25-66354 ◽

2017 ◽

Cited By ~ 1

Author(s):

Tulis Jojok Suryono ◽

Akio Gofuku

Keyword(s):

Flow Modeling ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Plant Behavior ◽

Influence Propagation ◽

Computer Based ◽

Virtual Display ◽

Multilevel Flow Modeling ◽

Propagation Rules ◽

Emergency Operating

Computer-based emergency operating procedures offer some benefits compared with the paper-based EOP. However, most of them do not fully provide clear and necessary information related to the procedure steps, such as future plant behavior and the affected components after taking an action of each step because of the limited space available on the virtual display unit. This paper investigates a technique to derive and indicate such kind of information using a Multilevel Flow Modeling model of simplified EOP of steam generator tube rupture accident of a pressurized water reactor plant. In this case, the MFM model is built based on operator’s action on each procedure step. Then, by using the influence propagation rules for function primitives of MFM model, the influenced functions of plant components necessary for confirming the procedure step can be gathered. This information will help operators to understand and take the actions in order to achieve the objective of each procedure step.

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MODELING OF OPERATOR’S ACTIONS ON A NUCLEAR EMERGENCY CONDITION USING MULTILEVEL FLOW MODELING

JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA ◽

10.17146/tdm.2019.21.1.5303 ◽

2019 ◽

Vol 21 (1) ◽

pp. 23

Author(s):

Tulis Jojok Suryono ◽

Sigit Santoso ◽

Restu Maerani

Keyword(s):

Situation Awareness ◽

Human Error ◽

Control Function ◽

Flow Modeling ◽

Functional Modeling ◽

Emergency Condition ◽

Control Functions ◽

Safe Condition ◽

Multilevel Flow Modeling ◽

Emergency Operating

In nulear emergency condition, after determining the initiating event and the type of the anomaly, operators should take counteractions to control the reactor to mitigate the accident and to bring back the plant to the safe condition. The actions should based on emergency operating procedures. In order to minimize the human error related to the actions, some necessary information is needed. Such kind of information is the consequence of the actions, which can be derived by modeling the counteractions. Multilevel flow modeling (MFM), a functional modeling, is chosen to model the counteraction with the consideration that it is based on cause-effect relations and consequence reasoning, it provides realization relationship which corresponds physical components with their functions, and it provides comprehensive diagnosis based on human perspective of the system objectives. The counteractions are represented by the control functions in the MFM. This paper discusses how to model the counteractions and the consequences of the actions to the system components, which are necessary to enhance situation awareness and to reduce human errors.Keywords: Operator actions, emergency operating procedures, multilevel flow modeling, control function, nuclear safety, human error

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