ML15040A727: Difference between revisions
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| issue date = 02/09/2015 | | issue date = 02/09/2015 | ||
| title = Attachment A.1 to Petition for Leave to Intervene - Leshinskie Cv | | title = Attachment A.1 to Petition for Leave to Intervene - Leshinskie Cv | ||
| author name = Leshinskie A | | author name = Leshinskie A | ||
| author affiliation = State of VT, Dept of Public Service | | author affiliation = State of VT, Dept of Public Service | ||
| addressee name = | | addressee name = | ||
| Line 14: | Line 14: | ||
| page count = 3 | | page count = 3 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:ANTHONY R. LESHINSKIE PO Box 714 Granby, CT 06035-0714 leshinar@sbcglobal.net Cellphone: +1 (860) 803-1108 www.linkedin.com/pub/tony-leshinskie/6/850/972/ | |||
Systems Simulation & Reactor Licensing Engineer Safety & Failure Mode Analysis | |||
* Finite Element Analysis | |||
* Regulatory Compliance | |||
* Apparent Cause Investigation Technical Support, Documentation & Technical Training | |||
* Engineering Proposal Development Computational Fluid Dynamics | |||
* Digital Instrumentation Evaluation | |||
* Equipment Change Impact | |||
* Quality Assurance Steam Systems Performance Analysis | |||
* Nuclear Power Plant Design | |||
* Radiological Dose Assessments Detail-oriented and proactive Systems Simulation and Regulatory Documentation Professional offering extensive experience in thermodynamic and thermal-hydraulic/fluid dynamics finite element analyses, qualitative evaluations, regulatory-compliance documentation and technical training material for power plant design basis and operating experience events. Proven abilities in quality assurance and problem solving while meeting stringent federal regulations (10 CFR 50 & Nuclear Regulatory Commission (NRC) guidance), ISO 9001 / NQA-1 standards and customer-defined requirements. Presently available to nuclear power industry companies seeking advanced / senior / principal engineers in the disciplines of reactor core design, power plant performance evaluation, control systems design, or equipment and regulatory compliance documentation. | |||
Computer Skills - Steam System Simulations, Analog & Digital Reactor Instrumentation Controls, Microsoft Office (Word, Excel, PowerPoint, Outlook), Windows XP, 7 & 8, Adobe Acrobat, Documentum, FORTRAN / Unix / Linux programming, GoToMeeting Webinars and Internet savvy. | |||
EXPERIENCE STATE OF VERMONT, PUBLIC SERVICE DEPARTMENT MONTPELIER & VERNON, VT STATE NUCLEAR ENGINEER & DECOMMISSIONING COORDINATOR, June 2014 to Present o Monitor the Vermont Yankee Nuclear Power Station's compliance with relevant federal and state regulations on behalf of the State of Vermont (and the general public residing within a 10-mile radius of the plant). | |||
o Provide technical information on Nuclear Power and its regulation to the Vermont Public Service Board, Public Service Department, relevant additional State Agencies and the general public. | |||
o Recommend modifications to State of Vermont Emergency Planning and Environmental Monitoring programs in response to Vermont Yankee's ongoing decommissioning. | |||
o Provide technical information and administrative support for the Vermont Nuclear Decommissioning Citizens Advisory Panel (NDCAP). | |||
o Evaluate Vermont Yankee Reactor License Amendment and Exemption Requests for impact on Vermont's Radiological Emergency Response Plan and their likely impact on the general public. | |||
o Represent Vermont at Regional & National conferences on Reactor Decommissioning, Radiological Emergency Planning and Radiological Waste Transportation. | |||
WESTINGHOUSE ELECTRIC COMPANY, LLC WINDSOR, CT (Previously known as ABB Combustion Engineering, Inc.) | |||
SENIOR ENGINEER, Transients and Design Analysis Department (and its predecessors) [1985 through 2013] | |||
Design Safety Analysis & Regulatory Compliance Activities: | |||
o As part of Original Equipment Manufacturer (Combustion Engineering / ABB / Westinghouse) organization, supported commercial power plant operations, nuclear fuel reloads and major equipment upgrades by delivering systems simulation products (FSAR Chapters 14/15, 10 & 7 support) and related regulatory documentation on over 150 projects. | |||
o Demonstrated compliance with ASME Pressure Vessel Code (Sections III & XI) and NRC Departure from Nucleate Boiling Ratio / | |||
Core Melt / Radiological Dose criteria for Combustion Engineering (CE) and Westinghouse-designed nuclear power plants using heat transfer, thermal-hydraulic and balance-of-plant computer simulations and engineering judgment. | |||
o Developed, maintained and verified system simulation code databases and plant equipment controller models for CE and Westinghouse AP1000-design plants (CENTS / CESEC-III / RETRAN-2W / LOFTRAN finite element analysis codes similar to RELAP). | |||
ANTHONY R. LESHINSKIE (continued) o Resolved over 100 equipment aging, plant start-up and plant operating issues through evaluations, instrumentation setting changes, operating procedure modifications and additional oral / written customer support; incorporating results into modification packages for nuclear power plants (e.g., 10 CFR 50.59 screenings and reports, reactor license amendments, Safety Analysis Reports, plant Technical Specifications / Operating Procedures changes, responses to NRC RAIs), often on short schedules. | |||
o Prepared and presented technology transfer training material (including step-by-step procedures) on over 20 selected Safety Analysis and Quality Assurance subjects for CE-fleet customers (Entergy, Palo Verde, San Onofre and Korea Nuclear Fuels Corp.) | |||
and Westinghouse internal use. | |||
o As safety analysis task leader, provided technical direction to a team of 3 to 5 engineers on 7 nuclear refueling projects. | |||
o As Safety Analysis Subject Matter Expert for San Onofre Units 2&3 (2002-2013) and Waterford Unit 3 (2007-2013) delivered analysis, regulatory documentation and training products on over 30 major projects and over 200 design basis evaluations. | |||
o As AP1000 Equipment Licensing Basis compliance team member (October 2012 to February 2013), confirmed that Chemical Volume Control System and Automated Depressurization System component requirements included in the AP1000 DCD Rev. | |||
19 complied with internal component specifications (10 CFR 52 compliance). | |||
o As HERMITE reactor core simulator Subject Matter Expert (a CE-fleet neutron diffusion model with several transient analysis options) addressed reduced coolant flow, power distortion and core design concerns for over 12 years. | |||
o As Program Engineer for STRIKIN-II reactor core simulator (a multi-node heat transfer and coolant flow channel simulator with thermal-hydraulic and critical heat flux correlation modeling options), addressed program functionality questions for over 7 years. | |||
o Addressed fuel pellet strain, clad strain and clad burst criteria on 4 different Westinghouse fuel products using STRIKIN-II code. | |||
o As departmental point of contact for Thermal Conductivity Degradation concerns (a high Burn-Up Fuel issue) in Westinghouse Fuel Performance Analysis methods, demonstrated CE-design PWRs compliance with new NRC requirements (August 2011 to June 2012). | |||
o Revised event analysis requirements to address Thermal Conductivity Degradation in Westinghouse Fuel Performance and Fuel Pellet Strain Analysis methods (August 2012 to February 2013). | |||
o Designed, Tested, Validated and Verified computer software and base deck data for the Core Protection Calculator System (a digital reactor shutdown system featuring dynamic compensation filters and direct calculation of engineering quantities significant to reactor safety) at CE-design PWRs (Arkansas Unit 2, Waterford Unit 3, Palo Verde, San Onofre, and 8 Korean plants). | |||
o Evaluated digital instrumentation system responses to design events, assuring safe plant operation on over 90 nuclear fuel reloads. | |||
o Additional project experience in reactor core design evaluation, fuel performance assessments and radiological dose calculations (including NRC Reg. Guide 1.183 and 1.195 standards). | |||
Quality Assurance & Business Development Activities: | |||
o Annually identified and implemented 1 to 3 rapid response project proposals based on customer concerns, providing a gross income of $50,000 to $120,000 per project for the previous 5 years. | |||
o Routinely interfaced with multiple engineering departments and customers, assuring error-free product delivery on-time and within budget, on over 90 projects. | |||
o As Departmental Coordinator for Engineering Impact & Evaluation (EIES) process, delivered evaluations, corrective action recommendations and new proposal estimates for over 6 years (process governed by 10 CFR 21 and 10 CFR 50.59). | |||
o As Westinghouse-Certified Apparent Cause Investigator, delivered corrective action and quality procedure improvement recommendations for over 8 years. | |||
o As Quality Assurance Lead on the initial CENTS model for AP1000 design; verified that information from design specifications and associated diagrams / drawings was correctly incorporated into database and controller parameters. | |||
o Conducted major revisions to 5 different departmental quality procedures (safety analysis standards) within 3 year period, employing human performance tools to address analysis error patterns identified via corrective action programs; with one procedure becoming a company-wide standard. | |||
o Departmental point-of-contact for 10 quality assurance audits (3 NUPIC, 2 ISO 9001 / Lloyds Registry, 5 internal) in which no significant deficiencies were identified. | |||
o Assessed new company-wide quality procedures for inclusion in departmental quality requirements (2011 to 2013). | |||
o Development team member on a major (1-year effort) Quality Assurance Procedure Manual (QAPM-101) revision implemented throughout ABB Combustion Engineerings Nuclear Fuels division. | |||
ANTHONY R. LESHINSKIE (continued) | |||
EDUCATION THE PENNSYLVANIA STATE UNIVERSITY UNIVERSITY PARK, PA o Awarded Bachelor of Science Degree in Nuclear Engineering, May 1984. | |||
o Earned eighteen credits beyond Bachelor's Degree requirements while working as Research Assistant. | |||
o As Research Assistant, developed computer control / data collection software on an experimental reactor water level gauge system; Operated experimental system during 4 loss of coolant accident tests at Idaho National Laboratory (Loss of Fluid Test facility). | |||
VOLUNTEER CAUSES & ORGANIZATIONS SOCIETY FOR CREATIVE ANACHRONISM, Northern & Eastern Connecticut Chapter (aka the Barony Beyond the Mountain chapter), [2003 through Present] | |||
o Volunteer in 1 public relations and 2 managerial positions within a 100+ member local chapter of an international, non-profit educational organization re-enacting the Medieval & Renaissance periods of European history. | |||
o Coordinate public demonstrations of local chapter activities that present arts, sciences and aspects of daily life from the Middle Ages & early Renaissance (including day-long demonstrations at the 2013 & 2014 Eastern States Exhibition, i.e. TheBigE.com). | |||
MANCHESTER COMMUNITY COLLEGE MANCHESTER, CT ADJUNCT FACULTY in Continuing Education Program o Beginner and intermediate ethnic dance class instructor since June 2001 o Medieval history class instructor since April 2010.}} | |||
Latest revision as of 15:56, 31 October 2019
| ML15040A727 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/09/2015 |
| From: | Leshinskie A State of VT, Dept of Public Service |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| 50-271-LA-2, RAS 27195, TBD | |
| Download: ML15040A727 (3) | |
Text
ANTHONY R. LESHINSKIE PO Box 714 Granby, CT 06035-0714 leshinar@sbcglobal.net Cellphone: +1 (860) 803-1108 www.linkedin.com/pub/tony-leshinskie/6/850/972/
Systems Simulation & Reactor Licensing Engineer Safety & Failure Mode Analysis
- Regulatory Compliance
- Apparent Cause Investigation Technical Support, Documentation & Technical Training
- Engineering Proposal Development Computational Fluid Dynamics
- Digital Instrumentation Evaluation
- Equipment Change Impact
- Quality Assurance Steam Systems Performance Analysis
- Nuclear Power Plant Design
- Radiological Dose Assessments Detail-oriented and proactive Systems Simulation and Regulatory Documentation Professional offering extensive experience in thermodynamic and thermal-hydraulic/fluid dynamics finite element analyses, qualitative evaluations, regulatory-compliance documentation and technical training material for power plant design basis and operating experience events. Proven abilities in quality assurance and problem solving while meeting stringent federal regulations (10 CFR 50 & Nuclear Regulatory Commission (NRC) guidance), ISO 9001 / NQA-1 standards and customer-defined requirements. Presently available to nuclear power industry companies seeking advanced / senior / principal engineers in the disciplines of reactor core design, power plant performance evaluation, control systems design, or equipment and regulatory compliance documentation.
Computer Skills - Steam System Simulations, Analog & Digital Reactor Instrumentation Controls, Microsoft Office (Word, Excel, PowerPoint, Outlook), Windows XP, 7 & 8, Adobe Acrobat, Documentum, FORTRAN / Unix / Linux programming, GoToMeeting Webinars and Internet savvy.
EXPERIENCE STATE OF VERMONT, PUBLIC SERVICE DEPARTMENT MONTPELIER & VERNON, VT STATE NUCLEAR ENGINEER & DECOMMISSIONING COORDINATOR, June 2014 to Present o Monitor the Vermont Yankee Nuclear Power Station's compliance with relevant federal and state regulations on behalf of the State of Vermont (and the general public residing within a 10-mile radius of the plant).
o Provide technical information on Nuclear Power and its regulation to the Vermont Public Service Board, Public Service Department, relevant additional State Agencies and the general public.
o Recommend modifications to State of Vermont Emergency Planning and Environmental Monitoring programs in response to Vermont Yankee's ongoing decommissioning.
o Provide technical information and administrative support for the Vermont Nuclear Decommissioning Citizens Advisory Panel (NDCAP).
o Evaluate Vermont Yankee Reactor License Amendment and Exemption Requests for impact on Vermont's Radiological Emergency Response Plan and their likely impact on the general public.
o Represent Vermont at Regional & National conferences on Reactor Decommissioning, Radiological Emergency Planning and Radiological Waste Transportation.
WESTINGHOUSE ELECTRIC COMPANY, LLC WINDSOR, CT (Previously known as ABB Combustion Engineering, Inc.)
SENIOR ENGINEER, Transients and Design Analysis Department (and its predecessors) [1985 through 2013]
Design Safety Analysis & Regulatory Compliance Activities:
o As part of Original Equipment Manufacturer (Combustion Engineering / ABB / Westinghouse) organization, supported commercial power plant operations, nuclear fuel reloads and major equipment upgrades by delivering systems simulation products (FSAR Chapters 14/15, 10 & 7 support) and related regulatory documentation on over 150 projects.
o Demonstrated compliance with ASME Pressure Vessel Code (Sections III & XI) and NRC Departure from Nucleate Boiling Ratio /
Core Melt / Radiological Dose criteria for Combustion Engineering (CE) and Westinghouse-designed nuclear power plants using heat transfer, thermal-hydraulic and balance-of-plant computer simulations and engineering judgment.
o Developed, maintained and verified system simulation code databases and plant equipment controller models for CE and Westinghouse AP1000-design plants (CENTS / CESEC-III / RETRAN-2W / LOFTRAN finite element analysis codes similar to RELAP).
ANTHONY R. LESHINSKIE (continued) o Resolved over 100 equipment aging, plant start-up and plant operating issues through evaluations, instrumentation setting changes, operating procedure modifications and additional oral / written customer support; incorporating results into modification packages for nuclear power plants (e.g., 10 CFR 50.59 screenings and reports, reactor license amendments, Safety Analysis Reports, plant Technical Specifications / Operating Procedures changes, responses to NRC RAIs), often on short schedules.
o Prepared and presented technology transfer training material (including step-by-step procedures) on over 20 selected Safety Analysis and Quality Assurance subjects for CE-fleet customers (Entergy, Palo Verde, San Onofre and Korea Nuclear Fuels Corp.)
and Westinghouse internal use.
o As safety analysis task leader, provided technical direction to a team of 3 to 5 engineers on 7 nuclear refueling projects.
o As Safety Analysis Subject Matter Expert for San Onofre Units 2&3 (2002-2013) and Waterford Unit 3 (2007-2013) delivered analysis, regulatory documentation and training products on over 30 major projects and over 200 design basis evaluations.
o As AP1000 Equipment Licensing Basis compliance team member (October 2012 to February 2013), confirmed that Chemical Volume Control System and Automated Depressurization System component requirements included in the AP1000 DCD Rev.
19 complied with internal component specifications (10 CFR 52 compliance).
o As HERMITE reactor core simulator Subject Matter Expert (a CE-fleet neutron diffusion model with several transient analysis options) addressed reduced coolant flow, power distortion and core design concerns for over 12 years.
o As Program Engineer for STRIKIN-II reactor core simulator (a multi-node heat transfer and coolant flow channel simulator with thermal-hydraulic and critical heat flux correlation modeling options), addressed program functionality questions for over 7 years.
o Addressed fuel pellet strain, clad strain and clad burst criteria on 4 different Westinghouse fuel products using STRIKIN-II code.
o As departmental point of contact for Thermal Conductivity Degradation concerns (a high Burn-Up Fuel issue) in Westinghouse Fuel Performance Analysis methods, demonstrated CE-design PWRs compliance with new NRC requirements (August 2011 to June 2012).
o Revised event analysis requirements to address Thermal Conductivity Degradation in Westinghouse Fuel Performance and Fuel Pellet Strain Analysis methods (August 2012 to February 2013).
o Designed, Tested, Validated and Verified computer software and base deck data for the Core Protection Calculator System (a digital reactor shutdown system featuring dynamic compensation filters and direct calculation of engineering quantities significant to reactor safety) at CE-design PWRs (Arkansas Unit 2, Waterford Unit 3, Palo Verde, San Onofre, and 8 Korean plants).
o Evaluated digital instrumentation system responses to design events, assuring safe plant operation on over 90 nuclear fuel reloads.
o Additional project experience in reactor core design evaluation, fuel performance assessments and radiological dose calculations (including NRC Reg. Guide 1.183 and 1.195 standards).
Quality Assurance & Business Development Activities:
o Annually identified and implemented 1 to 3 rapid response project proposals based on customer concerns, providing a gross income of $50,000 to $120,000 per project for the previous 5 years.
o Routinely interfaced with multiple engineering departments and customers, assuring error-free product delivery on-time and within budget, on over 90 projects.
o As Departmental Coordinator for Engineering Impact & Evaluation (EIES) process, delivered evaluations, corrective action recommendations and new proposal estimates for over 6 years (process governed by 10 CFR 21 and 10 CFR 50.59).
o As Westinghouse-Certified Apparent Cause Investigator, delivered corrective action and quality procedure improvement recommendations for over 8 years.
o As Quality Assurance Lead on the initial CENTS model for AP1000 design; verified that information from design specifications and associated diagrams / drawings was correctly incorporated into database and controller parameters.
o Conducted major revisions to 5 different departmental quality procedures (safety analysis standards) within 3 year period, employing human performance tools to address analysis error patterns identified via corrective action programs; with one procedure becoming a company-wide standard.
o Departmental point-of-contact for 10 quality assurance audits (3 NUPIC, 2 ISO 9001 / Lloyds Registry, 5 internal) in which no significant deficiencies were identified.
o Assessed new company-wide quality procedures for inclusion in departmental quality requirements (2011 to 2013).
o Development team member on a major (1-year effort) Quality Assurance Procedure Manual (QAPM-101) revision implemented throughout ABB Combustion Engineerings Nuclear Fuels division.
ANTHONY R. LESHINSKIE (continued)
EDUCATION THE PENNSYLVANIA STATE UNIVERSITY UNIVERSITY PARK, PA o Awarded Bachelor of Science Degree in Nuclear Engineering, May 1984.
o Earned eighteen credits beyond Bachelor's Degree requirements while working as Research Assistant.
o As Research Assistant, developed computer control / data collection software on an experimental reactor water level gauge system; Operated experimental system during 4 loss of coolant accident tests at Idaho National Laboratory (Loss of Fluid Test facility).
VOLUNTEER CAUSES & ORGANIZATIONS SOCIETY FOR CREATIVE ANACHRONISM, Northern & Eastern Connecticut Chapter (aka the Barony Beyond the Mountain chapter), [2003 through Present]
o Volunteer in 1 public relations and 2 managerial positions within a 100+ member local chapter of an international, non-profit educational organization re-enacting the Medieval & Renaissance periods of European history.
o Coordinate public demonstrations of local chapter activities that present arts, sciences and aspects of daily life from the Middle Ages & early Renaissance (including day-long demonstrations at the 2013 & 2014 Eastern States Exhibition, i.e. TheBigE.com).
MANCHESTER COMMUNITY COLLEGE MANCHESTER, CT ADJUNCT FACULTY in Continuing Education Program o Beginner and intermediate ethnic dance class instructor since June 2001 o Medieval history class instructor since April 2010.