Montreal Nuclear Services

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Level 1 PSA for Gentilly-2 NPP

GENTILLY-2

SCOPE

Develop Gentilly-2 site-specific level 1 PSA methodology and models.

DESCRIPTION

To be compliant with regulatory requirements from the Canadian Nuclear Safety Commission (CNSC), Hydro-Québec had to perform a detailed probabilistic safety assessment (PSA) to support the plant refurbishment.


The scope included

  • Performance of a risk baseline analysis
  • Use of Benefit-Cost Assessment (BCA) to rank design modification

  • Development of PSA methodologies (overall PSA methodology, fault tree guide, HRA methodology, CCF methodology, ASQ methodology)

  • Initiating event identification and frequency derivation

  • Event tree development

  • Mitigating Fault tree development and failure database integration

  • Accident sequence quantification (ASQ)

  • The models used up-to-date Gentilly-2 operation practises and existing fault tree models.​


The work was contracted by Hydro-Québec to AECL (Atomic Energy of Canada Ltd). 

NOTE:  This work was performed / lead by MNS personnel during their previous employment
OUTCOME
  • Methodolgoy was presented to CNSC and accepted

  • Level 1 PSA was completed

  • The PSA showed that Gentilly met the PSA core damage frequency safety goals

DISCIPLINES

  • Probabilistic Safety Assessment


CLIENT

Hydro-Québec

Gentilly-2, Canada


Timeframe

2008-2012


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