ML12335A391

Official Exhibit - NYS000291-00-BD01 - Curriculum Vitae of Dr. Franois J. Lemay (2011 Lemay Cv)

ML12335A391
Person / Time
Site:	Indian Point
Issue date:	12/21/2011
From:	Lemay F - No Known Affiliation
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21598, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12335A391 (4)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 NYS000291 Docket #: 05000247 l 05000286 Submitted: December 21, 2011 Exhibit #: NYS000291-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other:

FRANÇOIS J. LEMAY University of Birmingham (UK) Ph.D. Physics, Physics of Nuclear Reactors University of Birmingham (UK) M.Sc. Physics, Physics and Technology of Nuclear Reactors Ecole Polytechnique de Montreal B.Eng. Engineering Physics University of Montreal B.Sc. Physics Professional summary Dr. Francois Lemay is a professional engineer in the provinces of Ontario and Quebec.

His experience with MACCS consists of using the code to calculate the consequences to the population for several accidents scenarios in the context of the Nanticoke New Build Project for Bruce Power. With COSYMA, (a derivative of MACCS), similar calculations for ESKOM (South Africa), Hydro-Quebec (Canada), and the Canadian Navy were performed. He also used COSYMA to calculate the cost of accidents near Darlington and Gentilly for the Department of Natural Resources (NRCAN).\

Dr. Lemay instructs an advance level COYMA and MACCS course to Health Physicists and engineers..

Dr. Lemay has 27 years experience in:

Environmental Assessment o Authored shielding assessments, derived release limit calculations, dose assessment, risk assessment, project descriptions, technical support document for the radioactivity environmental component in support of the EA for the refurbishment of Gentilly-2, the new build projects at Bruce Power.

Operational Safety Assessments o Performed due diligence audit of Point Lepreau Nuclear Generating Station waste management program, including the SRWMF and the dry storage facility for the sale of Point Lepreau to Hydro Quebec; o Conducted integrated safety review (ISR) for Gentilly-2; o Conducted Operational Safety Review Team (OSART) audits of Forsmark Nuclear Power Station (Sweden);

Hazard Identification and Risk Assessment o Authored the risk assessment report for the transfer of spent fuel to the dry storage facility for the Spent Fuel Dry Storage Facility at Gentilly-2 nuclear generating station; o Authored the risk assessment report for the transfer of spent fuel to the dry storage facility at the Spent Fuel Dry Storage Facility at Cernavoda nuclear generating station. Also performed the shielding analysis for the CANSTOR modules and the consequence assessment for the crash of an aircraft on the storage facility.

o Authored the risk assessment report for the transfer of refurbishment waste to the storage facility for the expansion of the LLW and ILW waste storage facility for refurbishment waste at Gentilly-2 nuclear generating station. Performed

François Lemay shielding assessment for the refurbishment waste storage silos and transfer casks. Performed assessment of the degradation of the spent resin waste during 50 years of storage.

o Authored the risk assessment report for the refurbishment and continued operation of the Gentilly-2 nuclear generating station. This included an assessment of the risk from normal operation and accident situations.

Licensing o Contributor to Preliminary Safety Reports and Final Safety Reports for Gentilly-2, Chalk River reactors and isotope storage facilities; o Review of licensing submissions from Bruce for the CNSC Audits and evaluations o Conducted audits of emergency response plans and procedures for Gentilly-2, Point Lepreau, Durham region, Koeberg (South Africa);

Safety analysis and risk assessment o Conducted several deterministic safety studies and probabilistic safety assessments for the Canadian nuclear industry, including Gentilly-2, Point Lepreau, and Bruce.

Member of the CSA Technical Committee for the revision of the N288 series of standards.

Language English French Security clearance NATO Secret (level 2)

Selected experience by functional area Date Title Risk assessment Environmental Prepared the Radioactivity technical support Assessment of the document for the environmental assessment.

2006-2009 New Reactor Project at Performed risk assessment for normal the Bruce Power site operations and accident conditions.

Environmental Prepared the Radioactivity technical support Assessment of the document for the environmental assessment.

2009 New Reactor Project at Performed risk assessment for normal the Nanticoke site operations and accident conditions.

Co-author of the Technical Safety Review for the visits of nuclear powered vessel to Safety review of Canadian harbors. This included a level 3 2005-2006 French nuclear assessment of the consequences of severe powered vessels accidents and an evaluation of the safety program of the French Navy.

Prepared and delivered a four day course on Source term estimation 2006 source term estimation methods for severe methods for Candu-6 accidents situation in Candu-6 reactors.

International Safety Research Inc.

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François Lemay Prepared a risk assessment for the continued Environmental operation of the Gentilly-2 nuclear generating Assessment for the 2004-2006 station, derived release limit calculations, continued operation of shielding calculations and consequence Gentilly-2 assessment for accident situations.

Performed a risk analysis for the spent fuel dry AECL Cernavoda risk 2001 storage facility at the Cernavoda Nuclear analysis Generating Station in Romania.

Involved in the design and licensing of a dry storage facility for spent fuel at the Gentilly Nuclear Generating Station. Prepared the Risk Dry storage facility at Analysis, contributed sections of the 1993 the Gentilly nuclear Environmental Impact Statement, authored the generating station Shielding Analysis, and was co-author of the Safety Analysis Report. Expert witness on the radiological impact of the project during the public hearings.

Date Title Reactor physics Performed activation calculations for the end-shield components in support of the calandria Activation calculation 2010 replacement project at Bruce Power. Used for Bruce Power MCNP to obtain the neutron flux and the reaction rates in the activated components.

Performed activation calculations for the calandria replacement project. Created a full Activation calculation 2009 core model of the Bruce A reactors.

for Bruce Power Performed criticality calculation and obtained the activation products in the calandria.

Performed burnup calculations for French nuclear powered aircraft carrier Charles-de-2005 Burn up calculations Gaulle and the attack submarine Améthiste using the ORIGEN code.

Performed MCNP calculations for calibrating Reactivity feedback the model of the reactivity feedback of the 2000 calculation for RMC RMC slowpoke reactor using rhodium foil slowpoke reactor activation.

Date Title Radiation transport Shielding calculations Performed shielding calculations for the shield for the shield tank and 2010 tank, the end shield and shield tank storage the end shield at Bruce building using MCNP.

Power Shielding calculations Performed shielding calculations for the for the calandria 2009 replacement of the calandria for the Bruce A replacement project at Unit 1&2 reactors using MCNP.

Bruce Power Shielding calculations Performed shielding calculations for the 2006 for French nuclear hullshine in severe accident conditions from powered vessel the attack submarine Améthiste using MCNP.

International Safety Research Inc.

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François Lemay Shielding calculations Performed shielding calculations for the Spent for Cernavoda Fuel Dry Storage Area at the Cernavoda 2001 (Romania) spent fuel Nuclear Generating Station in Romania using storage facility MCNP.

Invited as an expert at the IAEA for the Consequences of preparation of a technical guide on 1998 severe accidents in consequences of severe accidents in CANDU-CANDU-600 reactors 600 reactors.

International Safety Research Inc.

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