Title: Combined Use of Probabilistic and Deterministic Methods in External events PSA
1Combined Use of Probabilistic and Deterministic
Methods in External events PSA
- Vladimir Morozov, Head of Safety Analysis
Division - Gennady Tokmachev, Chief Engineer of Safety
Analysis Division, - Igor Kalinkin, Head of EE Department in Safety
Analysis Division -
- JSC Atomenergoproekt, Moscow, RF
2About
- JSC Atomenergoproekt is an engineering company,
General Designer of nuclear power plants. - The company developed the designs of the majority
of NPPs in Russia, Eastern Europe and CIS
countries. JSC Atomenergoproekt is the General
Designer of the Bushehr NPP in Iran, Kudankulam
NPP in India, Akkuyu NPP in Turkey.
Atomenergoproekt is the General Designer and
General Contractor of the Novovoronezh-2 NPP
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3About
- PSA division (bureau) has over 25 year experience
in developing PSA for units with WWER power
reactors. - Operation conditions include power operation and
shutdown states. - At present time the scope of development include
internal level 1, level 2 and external events PSA.
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4Internal events PSA aids design and operation
- Aid to justification of design basis
- Initiating events selection and categorization
- Provide input to categorisation of SSC
- Aid to optimisation of system configurations
- Helps to provide justification of conditions for
safe operation (STI AOT)
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5Requirements of regulatory documents
- It should strive to have PSA estimated value for
severe BDBA frequencies less than 10-5 1/year
(NP-001-97- General provisions to ensuring NPP
safety) for the whole scope of events - PSA for external events must be developed to
obtain NPP accident risk assessment due to
external events (NP-064-05 Analysis of effects
of natural and man-induced external events on
nuclear energy objects.)
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6The scope of external events analysis
- Extreme natural events
- Seismic events
- High winds and tornadoes
- Extreme air and water temperatures
- External floodings, fires
- Extreme precipitation
-
- External man-induced events
- Air, road, water transportation incidents
- Industrial facility incidents
-
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7General procedure for external events analysis
- Is defined by national safety guide RB-021-01
Evaluation of reactor severe core damage due to
external events (at present time under revision) - It include
- Events selection and screening
- Hazard analysis
- Plant walkdowns
- Plant response and fragility analysis (if
required) - Bounding or detail analysis of accident sequences
based on modified level 1 models, core damage
estimation.
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8Event selection and screening
- Development of preliminary generic list of
external events - Analysis of site characteristics, preliminary
screening using RB-021-01 criteria A (distance
event cannot occur close to the site) ,B
(inclusion event is included in definition of
another event which already have been analyzed)
,C (time event is slow developing and plant
operating personnel have enough time to prevent
its consequences) - At preliminary stage only deterministic criteria
are used
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9Hazard analysis(seismic)
- Design base estimation is deterministic aimed to
conservative assessment of maximum design
earthquake (MRZ once per 10 000 years) and
design earthquake (PZ once per 1000 years)
according to NP-031-01 (Norms for design of
seismic resistant NPP) - Seismic hazard curves are developed according
classical PSHA approach - Along with seismic hazard response spectra is
also estimated - Global seismic hazard program results
(http//www.seismo.ethz.ch/static/GSHAP/) and
local seismological, tectonic and geological data
are used to develop models for analysis
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10Hazard analysis(seismic)
- Aleatory uncertainties include
- Attenuation law variabilities
- Seismic source characteristics (magnitude-length)
- Source location inside source zone
- Epistemic uncertainties (require development of
logic tree) - Source characteristic (active/not, linear or area
source, maximum magnitude determination) - Selection of attenuation law type
- Selection of parameters for source magnitude
occurrence rate law - Others
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11Example of logic tree for seismic hazard
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12Hazard curves after logic tree quantification
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13Example of percentile and mean hazard curves
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14Example hazard curve for maximum air temperatures
(Gumbel)
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15Uncertainty in hazard curve for minimum air
temperatures (Weibull)
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16Plant walkdown and seismic margin evaluation
(deterministic procedures)
- plant walkdowns in according to GIP-WWER
procedures (Balakovo unit 1) - Seismic margin evaluation using CDFM
(conservative definition of failure margins)
using EPRI NP-6041 SL1
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17Conditional failure probability (fragility)
- For seismic PSA using hybrid approach
- IAEA TECDOC-1487 Annex 1
- Kennedy, R.P., Overview of Methods for Seismic
PRA and Margin Assessments Including Recent
Innovations, Proceedings of the OECD-NEA Workshop
on Seismic Risk, Tokyo, Japan, August 1999 - Load strength model or FORM (first order
reliability methods) for others
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18Some results for EE PSA (Balakovo unit1
Novovoronezh-2 unit 1)
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19- Thank you for attention !
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