Rebecca L. Steinman, PhD, PE, CEM
Senior Engineering Consultant
Experience Summary
Dr. Steinman has over ten years of nuclear industry experience related to licensing, analysis, corrective action, operational support, and research. Her areas of expertise include new plant licensing [design certifications (DCDs) and combined license (COL) applications], design basis document (DBD) programs, environmental qualification (EQ), fire protection, thermal-hydraulic analyses and room heat-up calculations, and 10 CFR 50.59 reviews. She has been a major contributor to the EQ Programs of two nuclear power stations. She has performed these types of activities at both PWR and BWR facilities.
Dr. Steinman is a current IEEE working group member, participated in a lead role for the effort to update IEEE Std 627 (Equipment Qualification) for use by new plants, and is currently in a lead role for the ongoing effort to revise IEEE Std 1205 (Aging Management). She is also a registered professional engineer in Michigan.
Education
PhD, Nuclear Engineering & Radiological Science, University of Michigan
MS, Nuclear Engineering, University of Michigan
MEng, Radiological Health Engineering, University of Michigan
BS, Nuclear Engineering, University of Missouri-Rolla
Registrations/Certifications
- Professional Engineer, MI Number 6201050031 Earned 2003
- Certified Energy Manager (CEM) by the Association of Energy Engineers – 2002
Training
10 CFR 50.59 Evaluation Certified by LeBlond and Associates, LLC - 2002
Corporation project Experience
Senior Engineering Consultant, 2009 to present
Tetra Tech Advent, Ann Arbor, MI
Assisting a reactor vendor in developing a DCD and related support documentation for a new reactor design, primarily in the area of non-LOCA accident analysis and associated dose evaluations. Assist a reactor vendor in the development of Emergency Operating Procedures (EOPs) and corresponding support documentation for a new reactor design. Assist in responding to Nuclear Regulatory Commission (NRC) requests for additional information, as well as preparing material for NRC and Advisory Committee on Reactor Safeguards (ACRS) meetings and audits. Design verifying calculations in support of the HELB and room heat-up analyses at Prairie Island. Reviewing environmental qualification documentation for components installed and used in safety-related applications in nuclear power plants.
Engineering Consultant, 2006 to 2009
Tetra Tech Advent, Ann Arbor, MI
Assisting a reactor vendor in developing a DCD for a new reactor design, primarily in the area of non-LOCA accident analysis. Assist in responding to Nuclear Regulatory Commission (NRC) requests for additional information. Responsible for the checking and design verification of two large-scale thermal-hydraulic analyses using the GOTHIC computer software to define post-accident environmental conditions.
Senior Engineer, 2002 to 2006
Tetra Tech Advent, Ann Arbor, MI
Performed research in support of reconstituting EQ Program design basis requirements. Assisted in formulating and re-establishing design requirements and bases in areas of EQ accident definition, radiation environment dosage, harsh/mild criteria, codes & standards and regulations, EQ Master List control, and EQ Program maintenance. Was a major contributor to resolution of corrective actions implemented in support of resolution of EQ issues at Davis-Besse.
Performed a complex analysis of Arrhenius-weighted average containment normal service condition temperatures based on six years worth of individually assessed daily temperature values. The result allowed an evaluation of both local area and elevation effects, as well as an accurate assessment of margin, for future qualified life determinations. Prepared EQ file updates to reflect changes in normal temperature conditions.
Assisted in research on assessing aging of electric cable insulation culminating in technical papers presented at four international conferences. Researched and evaluated modeling approaches for determining maximum temperatures within electronic cabinets. Assisted in performing a major revision of a nuclear plant’s Updated Safety Analysis Report.
Engineer Level II, 1999 to 2002
Tetra Tech Advent, Ann Arbor, MI
Implemented a spreadsheet approach and methodology for evaluating area temperature effects with respect to equipment aging and post-accident operability at the Davis-Besse Nuclear Power Station. Participated in DBD preparation at the Kewanee Nuclear Power Plant. Responsibilities included preparing design calculations, performing engineering evaluations, and preparing licensing basis document changes.
Previous Experience
Graduate Assistant / Engineering Intern / Research Scientist, 1994 to 1999
Universities of Michigan and Missouri-Rolla, Argonne and Sandia National Laboratories, Waste Management Federal Services, and Forschungzentrum KFA Juelich.
Validated radiation dose models using dose measurements from transient sources. Developed transportation risk estimates using RADTRAN and evaluated output sensitivity to detail of accident rate data. Developed and maintained radiation dose and contamination records. Calculated creep strain parameters for German reactor pressure vessels and prepared technical report for later use in a joint study with the French.
Professional Affiliations/Achievements/Awards
- Member, American Nuclear Society (ANS) and Chair, Michigan Section (2004-2006)
- Treasurer, ANS Michigan Section (1999-2004 and 2006-2008)
- Executive Committee Member and Program Committee Chair, American Nuclear Society Environmental Sciences Division (2004-2010)
- Member, ANS Professional Engineering Exam Committee (PEEC) (2010-2013)
- Steering Committee Executive Director and Publicity Chair, 2002 ANS International Topical Meeting on Probabilistic Safety Assessment
- Technical Program Committee Chair, 2008 ANS International Joint Topical Meeting on Emergency Preparedness & Response and Robotic & Remote Systems
- Member, Institute of Electrical and Electronic Engineers (IEEE)
- Member and Officer, IEEE Nuclear Power Engineering Committee Working Group SC-2.10 (Design Qualification) responsible for IEEE Std 627 (Equipment Qualification)
- Member and Officer, IEEE Nuclear Power Engineering Committee Working Group SC-3.4 (Aging Management) responsible for IEEE Std 1205 (Assessing, Mitigating, and Managing Aging)
- Member, IEEE Nuclear Power Engineering Committee Working Group SC-2.1 (Equipment Qualification) responsible for IEEE Std 323 (Class 1E Equipment Qualification)
- Member, IEEE/IEC SC45A WGA10 (Condition Monitoring) responsible for IEC 62582 Series Standards
- IEEE Technical Committee Prize Paper Award for "Computerized Approach to Updating Qualified Lives for EQ Equipment" (2003)
- Member, Women in Nuclear (WIN)
- Member, Tau Beta Pi Engineering Honorary Society Alumni
Peer Reviewed Publications
- Steinman, RL, DA Horvath, and MJ Wylie, “Standardization of EQ Program Limitorque Valve Actuator Configurations,” IEEE Transactions on Nuclear Science, 51(4): 1857-1859, August 2004.
- Horvath, DA, MJ Wylie, and RL Steinman, “Restoring Environmentally Qualified Equipment Health After a Boric Acid Event,” IEEE Transactions on Nuclear Science, 50(4): 1960-1863, August 2004.
- Wylie, MJ, RL Steinman, and L Makatura, “Computerized Approach to Updating Qualified Lives for EQ Equipment,” IEEE Transactions on Nuclear Science, 50(4), August 2003.
- Steinman, RL, RL Weiner, and KJ Kearfott, “Comparison of Transient Dose Model Predictions and Experimental Measurements,” Health Physics Journal, 83(4): 504-511
- Steinman, R.L. "Evaluation of the Radiological Risks Associated with the Routine Transport of Radioactive Material with Michigan" [dissertation]. Ann Arbor (MI): University of Michigan; 2000.
Conference Presentations
- “Professional Engineering Licensure…Opening Doors of Opportunity”, ANS 2010 Annual Meeting Transactions, June 13-17, 2010, San Diego, CA by RL Steinman “Evacuation Time Estimate Analysis for the Fermi 2 Emergency Planning Zone,” ANS 2004 Annual Meeting Transactions, June 13-17, 2004, Pittsburgh, PA by RL Steinman and GM Hostetter
- “Re-establishing EQ Regulatory Compliance for a Boric Acid Release Event,” 2003 Nuclear Science Symposium & Medical Imaging Conference, October 19-25, 2003, Portland, OR by MJ Wylie, DA Horvath, and RL Steinman
- “Restoring Health to Containment EQ Equipment After a Boric Acid Release Event,” 2003 Nuclear Science Symposium & Medical Imaging Conference, October 19-25, 2003, Portland, OR by DA Horvath, MJ Wylie, and RL Steinman
- “Standardization of EQ Program Limitorque Valve Actuator Configurations,” 2003 Nuclear Science Symposium & Medical Imaging Conference, October 19-25, 2003, Portland, OR by RL Steinman, DA Horvath, and MJ Wylie
- “State of the Art Techniques for Nuclear Emergency Planning Population Analysis,” 2002 Nuclear Science Symposium & Medical Imaging Conference, November 10-16 2002, by RL Steinman
- “Computerized Approach to Updating Qualified Lives for EQ Equipment,” 2002 Nuclear Science Symposium & Medical Imaging Conference, November 10-16 2002, by MJ Wylie, RL Steinman, and L Makatura
- "Are You Managing Your Information or Your Paper? - Letting Go of the Page Paradigm" ANS 2002 Annual Meeting Transactions, June 9-13 2002, Hollywood, FL by DC Wood and RL Steinman
- “Risk Assessment for Aircraft Electrical Interconnect Subsystems,” International Conference on Wire System Aging, April 23-25 2002, Bethesda, MD by DC Wood and RL Steinman
- “Microstructure Assessments for Determining Electric Cable Insulation Remaining Life,” International Conference on Wire System Aging, April 23-25 2002, Bethesda, MD by DA Horvath and RL Steinman
- “Assessing the Condition of Inaccessible Cables Through Correlation of Capacitance and Insulation Microstructure,” International Conference on Wire System Aging, April 23-25 2002, Bethesda, MD by RL Steinman and DA Horvath
- "Relationship of Electrical Insulation Void Content with Electric Cable Normalized Capacitance," 2001 IEEE Conference on Electrical Insulation and Dielectric Phenomena (CEIDP), October 14-17, 2001, Kitchner, Ontario, Canada by DA Horvath and RL Steinman
- "Feasibility of Determining Margin of Remaining Life Using Void Content," IEEE Symposium on Nuclear Power Systems, November 4-10, 2001, San Diego, California, USA by RL Steinman and DA Horvath
- "A Comparison of the RADTRAN 5 and Riskind 1.11 Incident-Free Dose Models," Proceedings of Waste Management 2000 Symposium, 27 February - 2 March 2000, Tucson, Arizona, USA by RL Steinman and KJ Kearfott
- "Risk Assessment for Sample WIPP and Yucca Mountain Shipments," Proceedings of the Waste Management '99 Symposium, 28 February - 4 March 1999, Tucson, Arizona, USA by RL Steinman and RF Weiner,
- "Experimental Validation of the RADTRAN 5 Incident-Tree and Handler Dose Models, Transactions of the American Nuclear Society, 14-18 November 1999, Long Beach, CA: 81(67): 67-68 by RL Steinman, JL Boles, JG McFadden, RF Weiner, and KJ Kearfott
- "Sample Transportation Risk Assessments for WIPP And Yucca Mountain Shipments," 1999 Health Physics Society Annual Meeting, Philadelphia, PA, USA by RL Steinman, RF Weiner, and KJ Kearfott
|