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2nd Asian Conference on Safety and Education in Laboratory ...drrc.ui.ac.id/acsel/lister/Oral...
Transcript of 2nd Asian Conference on Safety and Education in Laboratory ...drrc.ui.ac.id/acsel/lister/Oral...
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
Aneziris, O. N., Housiadas, C., Stakakis, M., Papazoglou, I. A. (2004). Probabilistic safety analysis of a Greek Research Reactor. Annals of Nuclear Energy, 31(5), 481-516. doi: 10.1016/j.anucene.2003.09.003
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
IAEA. (1987). Probabilistic Safety Assessment to Research Reactor TECDOC-400. Vienna.
IAEA. (2005). Safety of Research Reactor NS-R-4. Vienna.
IAEA. (2014). Safety Reassessment for Research Reactors in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant No. 80.
Jeong K.S., Lee D.S., Lee K.W., Lim H.K.,. (2008). A Qualitative Identification And Analysis Of Hazards, Risks And Operating Procedures For A Decommissioning Safety Assessment Of A Nuclear Research Reactor. Annals of Nuclear Energy 35, 1954–1962.
PRSG. (2011). Laporan Analisis Keselamatan (LAK) RSG-GAS Rev 10.1: PRSG.
Rao V. Kolluru, Steven M. Bartell, Robin M. Pitblado, R. Scott Stricoff. Risk Assessment and Management Handbook For Environmental, Health and Safety Professionals.: McGraw-Hill,Inc.
References