HAZARD IDENTIFICATION OF PRIMARY COOLING SYSTEM

G.A SIWABESSY REACTOR AS PART OF SAFETY ANALYSIS

FOR PREVENTING AND MINIMIZING THE ACCIDENT IMPACT

Ratih Luhuring Tyas, Heri Hermansyah, Geni Rina Sunaryo

University of Indonesia

National Nuclear Energy Agency

Depok, 1-2 December 2015

2nd Asian Conference on Safety and Education in Laboratory

Backgrounds

Objectives

Methods

Results

Conclusions

Outlines

Backgrounds

Objectives

The Objevtives from this study:

• Hazard identification and analysis of the primary cooling system RSG-GAS

• Determine Postulated Initiating Event of the primary cooling system RSG-GAS

Metods - Hazard Identification

Description Potential Hazard Cause

Facility / System

1.1.

2.

2. dst

Metods - HAZOP

Review P&ID Deviation CauseProtection

SystemDocumentation

Overview Primary Cooling System

REACTOR BUILDING

Overview Primary Cooling System

Results – Hazard Identification

Potential Hazard

PumpsFailure of pumps and rupture of

pump casing.

Heat Exchanger

Heat Exchanger Leakage

PipeLeakage of the boundary beyond

the isolation valves

ValveInadvertent closure of the primary

isolation valves

Hasil dan Pembahasan

No Description Potential

Hazard

Cause

1. Leakage of the primary coolant

boundary beyond the isolation valves.

Loss of coolant Corrosion, fatique, fracture,

aging

2 Rupture of a pump casing due to

impeller failure;

Loss of coolant Corrosion, fatique, fracture,

aging

3. Heat Exchanger Leakage Loss of coolant Corrosion, fatique, fracture,

aging

4. Loss of Primary pump Loss of flow Maintenance and Inspection

are not good

5. Inadvertent closure of the primary

isolation valves

Loss of flow Maintenance and Inspection

are not good

Results – Hazard Identification

Hasil dan Pembahasan

1 Node

Rate of Mass Flow ≤ 90% ± 5% (normal 860 kg/ds )

Control of Mass Flow JE-01 CF 811/821/831

Water Level in The Reactor ≤ 12,25 m ± 0,05 m

Control of Water Level JAA-01 CL 811/821/831

Position of Primary System Isolation Valves 3o.

Control of Position of Isolation Valves JE-01 CG 811/821/831 dan JE-01 CG

812/822/832

Temperature at Heat Exchanger

outlet> 44 oC

Control of Temperature at Heat Exchanger outlet JE-01

CT 811/821/831.

Results – Hazard Analysis

Deviation Cause Consequence Protection System

Node : 1. Primary Cooling Systems

1.1 No/ less flow of core inlet Rupture of pump

casing

Leakge of pipe

Loss of primary pump

Loss of coolant

Loss of coolant

Loss of flow

JE-01

CF 811/821/831

JAA-01

CL 811/821/831

JE-01

CF 811/821/831

1.2 Less flow of core outlet closure of the primary

isolation valves

Loss of flow JE-01

CG 811/821/831

JE-01

CG 812/822/832

1.3 High temperature outlet of

Primary Heat Exchanger

Heat Exchanger

Leakage

Loss of coolant JE-01

CT 811/821/831

Results – Hazard Analysis

No. Event Group Postulated Initiating Event

1. Loss of Coolant Accident

(LOCA)

1. LOCA because the leakage of the primary coolant

boundary beyond the isolation valves;

2. LOCA because the rupture of a pump casing due to

impeller failure;

3. LOCA because heat exchanger leakage;

2. Loss of Flow Accident

(LOFA)

1. LOFA because the loss of primary pump, and

2. LOFA because the inadvertent closure of the

primary isolation valves.

Conclusions – Postulated Initiating Event

I would like to thank to :

PRSG-BATAN for the permission using the data and documents

Acknowledgement

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Chatzidakis A., Ikonomopoulos A. (2013). Phenomenological Investigation Of Loss Of Coolant Accident In A Research Reactor Facility. Nuclear Engineering and Design, 256, 341-349. doi: 10.1016/j.nucengdes.2012.08.025

Hashemi-Tilehnoee, M., Pazirandeh, A., Tashakor, S. (2010). HAZOP-study on heavy water research reactor primary cooling system. Annals of Nuclear Energy, 37(3), 428-433. doi: 10.1016/j.anucene.2009.12.006

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IAEA. (2014). Safety Reassessment for Research Reactors in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant No. 80.

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PRSG. (2011). Laporan Analisis Keselamatan (LAK) RSG-GAS Rev 10.1: PRSG.

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References