Lovell Gilbert, P. Eng. Email & Phone Number

Tiverton, Ontario, Canada

Duties included:- Operating Limits and Conditions (OLC) implementation - Technical content owner of the station Impairments Manuals which define the levels impaired conditions of operations- Environmental Qualification (EQ) Program safety case and room conditions analysis- Fuel cooling, heat sinks and coolant flows requirements- Plant safety analysis- Containment boundary requirements- Plant seismic safety case- Fire Safe Shutdown Assessment (FSSA)- Safe Operating Envelope Program- Severe Accident Management Guidance (SAMG) Program development and implementation- Outage heat sinks requirements - Regulatory communications- Apparent Cause Analyses - Business planning- Contract management

Tiverton, Ontario, Canada

Duties included:- Contract management - Severe Accident Management (SAM) Program- Operating Limits and Conditions- Fire Shutdown Safety Analysis (FSSA) review- Environmental Qualification (EQ) Program - Seismic safety case- Engineering Change Control- Regulatory Compliance

Tiverton, Ontario, Canada

Duties included:- Implementation of the New Reliability Equipment Program (NuREP) for equipment/system reliability data collection and fault typing- Plant reliability reporting-Regulatory, codes and standards compliance management - Business planning

Vienna, Austria

Lecturer for Training Workshop on the Development of Severe Accident Management Guidelines Using the IAEA's Severe Accident Management Guideline Development ToolkitMember of expert consultant working group for production of the following:- Specific Safety Guide - No. SSG-69 - Equipment Qualification for Nuclear Installations- Specific Safety Guide - No. SSG-54 - Accident Management Programs for Nuclear Power Plant- Safety Reports Series No. 32 – Implementation of Accident Management Programs in Nuclear Power Plants- TECDOC-1930 - Implementation and Effectiveness of Actions Taken at Nuclear Power Plants Following the Fukushima Daiichi Accident- TECDOC-1812 - Severe Accident Mitigation through Improvements in Filtered Containment Vent Systems and Containment Cooling Strategies for Water Cooled Reactors- TECDOC No. 1770 – Design Provisions for Withstanding Station Blackout at Nuclear Power Plants- TECDOC-1791 – Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants- TECDOC-1818 - Assessment of Equipment Capability to Perform Reliably under Severe Accident Conditions- Consultancy Meeting on the Review of Applicability of Safety Standards to Novel Advanced Reactors - Parts 1, 2 and 3- International Experts’ Meeting on Severe Accident Management in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant- Technical Meeting on Accident Management for Advanced Reactors- Technical Meeting on the Verification and Validation of Severe Accident Management Guidelines

Toronto, Ontario, Canada

Toronto, Canada Area

Toronto, Ontario, Canada

- CSA N290.16 – Requirements for Beyond Design Basis Accidents (BDBA)- CSA N290.6 – Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the event of an Accident- CSA N1600 – General Requirements for Emergency Management for Nuclear Power Plants- CSA N290.11 – Requirements for the Reactor Heat Removal Capability during Maintenance Outages of Nuclear Power Plants- CSA N290.2 – Requirements for Emergency Core Cooling Systems for Nuclear Power Plants- CSA N290.0 – General Safety Requirements for Nuclear Power Plants- CSA N290.13 – Standard on Environmental Qualification

Toronto, Ontario, Canada

The Technical Committee on “Risk and Safety Management” is responsible for developing and maintaining standards related to risk and safety management at nuclear reactor facilities and the associated analyses and methodologies.

Toronto, Canada Area

The CANDU Owners Group (COG) is a private, not-for-profit corporation funded voluntarily by CANDU operating utilities worldwide. COG and its members work together with suppliers and other stakeholders to solve the industry’s most challenging technical problems, share operating experience and work toward regulatory acceptance through collaboration.The objectives of the SAMG/BDBAM Task Team are as follows:- To review COG SAMG Technical Basis Documents and update as required- To develop common approaches to deal with evolving SAM Guidance issues and requirements- To use the task team experiences to assist international working group members with meeting regional regulatory requirements- To provide a forum for discussion of Beyond Design Basis Nuclear Safety Enhancements and Beyond Design Basis Accident response- To provide industry comment on new or proposed changes to existing related national and international Regulatory documents

Toronto, Ontario, Canada

Deliver Severe Accident Management Guidelines (SAMG) lectures

Education record

Bachelor Of Engineering (B.Eng.), Mechanical Engineering

Bachelor Of Science (B.Sc.), Physics