Douglas C. Wood, PE

Principal Consultant

Experience Summary

Mr. Wood has over 35 years of commercial nuclear power industry experience related to licensing, analysis, assessments, design, and operational support derived from work at a reactor vendor, a major A/E, and a senior level consulting company. His specialties include maintenance and use of current licensing bases, independent technical and program reviews, facility safety analysis, design basis document (DBD) programs, environmental qualification, probabilistic risk assessment (PRA), nuclear plant fire protection safe shutdown analysis, non fire safe shutdown risk analysis, 10 CFR 50.59 reviews, licensing support for design and operational issues, and project management of complex multi-discipline engineering problems.

His experience during seven years with an NSSS vendor included reactor control and protection system functional design, plant accident and transient response simulation, and plant and containment level PRAs. His experience during eight years with a major A/E included assisting 11 nuclear utilities at 13 plants in performing PRAs, safe shutdown system analyses, hazards analysis, environmental qualification (EQ), and DBD activities.  His consulting experience includes design and licensing basis, configuration control, fire protection, EQ, station blackout, safety analysis, PRA, and system design issue-related tasks for 12 nuclear utilities at 13 plants.  Concurrently, he is supporting the new generation of nuclear plants in the US through a NSSS design certification, various combined license licensing activities, and preparation of new-build specifications and contractual documents.

Mr. Wood is a registered professional engineer in three states, a Certified Energy Manager, and a certified nuclear QA lead auditor.  He also serves as the non-university member on the University of Michigan Ford Nuclear Reactor Safety and Decommissioning Review Committees, and is an elected member of the Penn State Nuclear Engineering Society Board of Directors.

Education
MS, Nuclear Engineering, University of Michigan
BS, Nuclear Engineering, Pennsylvania State University

Registrations/Certifications

• Security Clearance, NRC, Type Q (November 2009 - July 2010)
• Professional Engineer, MI Number 29450 Earned 1982
• Professional Engineer, IL Number 7569378 Earned 1986
• Professional Engineer, OH Number 56284 Earned 1992
• Society of Fire Protection Engineers (SFPE) – Professional Member (Certificate 10266)
• 10 CFR 50.59 Evaluation Certified by LeBlond and Associates, LLC (2002)
• ANSI N45.2.23 and NQA-1-1989 Certified Lead Auditor (1992)
• Association of Energy Engineers – Certified Energy Manager (2004), Certified Green Building Engineer (2005), Certified Business Energy Professional

Corporations Project Experience

Principal Consultant / Senior Project Manager, 1990 - Present
Tetra Tech Advent, Ann Arbor, MI

Recent accomplishments include providing senior consulting services related to non-LOCA accident analysis in support of a new reactor NRC Design Certification, supporting the development of Emergency Response Guidelines, Emergency Operating Procedures, and Severe Accident Management Guidelines for an advanced reactor in the US,  supporting US Combined License applicants with licensing and new-build contracts, performing reviews in support of recent NRC Design Basis Threat security orders, supporting the design and licensing of a dry fuel storage facility, and serving as one of five commercial nuclear power experts in the independent licensing review of the Yucca Mountain waste repository’s surface facility that will accept and pre-process nuclear waste for underground storage.  

Managed and participated in nine DBD preparation, validation, and open item resolution projects for four nuclear utilities; resolved technical issues, reviewed procedures for effectiveness, and provided technology transfer and training related to nuclear safety analysis for six major projects at a multi-unit nuclear plant site; facilitated an engineering process improvement benchmarking program for a nuclear utility, and performed an independent assessment of a UFSAR Validation Project and a UFSAR Accident Analysis Chapter 15 Rewrite Project.  

Managed and technically supported nuclear plant fire protection program rebaseline and enhancement projects for several nuclear sites.  These projects included comprehensive fire protection program self-assessments, fire protection safe shutdown analysis, component and cable database updates and refinements, safe shutdown system performance calculations, development and validation of safe shutdown operator action timelines, manual action feasibility evaluations, and NRC inspection support.

Was a principal author of a nuclear plant owner’s 1996 10 CFR 50.54(f) design configuration letter response and has subsequently supported UFSAR validation projects and configuration control enhancements in response to the resulting commitments. Performs special assignments to support licensees in addressing high-profile NRC generic and plant-specific emergent issues.

As VPQA (head of Advent's Corporate Quality Assurance Program), is responsible for performing independent assessments and audits of Advent's quality projects.

Fire Protection Experience
Commercial Nuclear Power Industry (* designates “responsible charge” level of responsibility experience)

08/2006    Participant, NEI Fire Protection Information Forum, San Francisco, CA (including additional conference for NFPA 805 conversion)

08/2006    Participant, NEI Fire Protection Information Forum, San Francisco, CA

10/2005 – 12/2005    *Project Engineer, Fermi 2 Nuclear Power Plant Detection Evaluations (Advent)

• Prepared calculations that used fire modeling tools to evaluate the functional adequacy of fire detection systems not in complete compliance with NFPA-72

10/2005    Received training, including a practical workshop, on the use of numerical fire modeling tools for use in nuclear power plants (Advent)

1/2003 – 12/2005    *Project Engineer for Fermi 2 Fire Protection Improvement Program (Advent)

• Lead for Fermi 2 Fire Protection Program self-assessment (fire systems, safe shutdown capability, and associated procedures and corrective actions) that served as the basis for the scope of the project
• Task Supervisor for fire detection (NFPA-72D, E) and wet pipe sprinkler (NFPA-13) code compliance reviews.  Participated in field walkdowns and reviewed final reports in parallel with client’s Fire Protection Engineer acceptance review.
• Prepared, revised, and checked calculations demonstrating compliance with Nuclear Regulatory Commission fire protection regulatory guidance and the associated Fermi 2 licensing basis.
• Evaluated adequacy of specific fire barrier systems and installation details for their application as electrical raceway fire separation barriers.

09/2003    Participant, NEI Fire Protection Information Forum, Baltimore, MD

2/1997 – 12/2002    Project Engineer for Point Beach Nuclear Plant Fire Protection Rebaseline Program (Tetra Tech Advent)

• Member of a consultant team to assess the technical adequacy of the Point Beach fire protection program and associated documentation.  The report from this activity served as the basis for the remaining tasks in the Fire Protection Baseline
• * Supervised an engineering team that developed a hydraulic model of the Point Beach fire water distribution system using the ProtoFlo program, and its subsequent application to reconcile anomalies in observed flows during system performance tests.
• *Prepared, supervised, reviewed, or approved approximately 20 fire protection and nuclear plant system performance calculations to document satisfying their respective design functions.
• *Prepared and supervised the preparation of fire-related and non-fire-related room heatup calculations for the purpose of determining the impact of temperature and/or smoke and gas layer characteristics on equipment operability and human habitability.
• Reviewed calculations for post fire portable ventilation systems for smoke removal and post-fire temperature control (with loss of normal ventilation)

7/1995-3/1996    Project Manager for Palisades Nuclear Plant Fire Protection Safe Shutdown Performance Analyses (Tetra Tech Advent)

• Prepared, supervised, reviewed, or approved approximately 40 fire protection and nuclear plant system performance calculations to document satisfying their respective design functions.

11/1993 – 12/1994    *Project Manager for Point Beach Design Basis Document Project (Tetra Tech Advent)

• Co-authored Fire Protection Design Basis Document, which covered both topical requirements related to nuclear plant safe shutdown as well as chapters on each major fire protection system (water suppression, gaseous suppression, detection and alarm, foam suppression, water distribution, hose racks and reels, portable extinguishers, and dedicated shutdown system for fires requiring evacuation of the control room)
• Performed in-plant validation for selected portions of the Fire Protection Design Basis Document (to verify the design bases were being met)

1989 – 1990    Fire Protection Licensing Lead for Davis-Besse Nuclear Plant (Tenera)

• Coordinated the closure of regulatory commitments related to compliance with 10 CFR 50 Appendix R fire protection safe shutdown and the classical Fire Hazards Analysis.  The work included (but was not limited to) field, technical, and administrative activities related to suppression, detection, spatial separation of combustibles and safe shutdown cables, fire shutdown procedures, fire drills, emergency communications equipment, fire brigade equipment and training, QA audits, and fire barriers.

1984 – 1988    Fire Protection Design & Analysis Lead for Duane Arnold Energy Center Appendix R Regulatory Compliance (Bechtel)

• Performed complete update and reformatting for the plant Fire Hazards Analysis Report, including fire zone boundary requirements, combustible loadings, fire durations,  and incorporation of safe shutdown strategies.
• Developed methodology for fire barrier functional evaluations in support of FHA and safe shutdown analysis
• Developed methodology for analyzing structural steel response to cable tray fires and specified requirements for localized application of structural steel fireproofing.  Supported the plant in obtaining NRC approval for the approach.
• Evaluated the design of a water curtain system as an alternative t a rated fire barrier.  Supported the plant in obtaining NRC approval.
• Fire protection engineering evaluation of untested gasket as part of a non-UL labeled watertight door.
• Evaluated adequacy of emergency lighting  for post-fire egress and field tested emergency radios, repeaters, and sound-powered pjones for adequacy in fire fighting and plant shutdown.
• Performed field surveillances for fire doors (NFPA-10)
• Evaluated installation deviations from tested configurations for electrical raceway fire barriers.
• Served as plant interface for NRC baseline fire protection inspection.

1983 – 1984    Fire Protection Lead Design & Analysis Engineer for Midland Nuclear Power Plant (Construction Phase)

• Overall responsibility for the Midland fire protection safe shutdown analysis.  Supervised a team of 6 engineers and interfaced with construction disciplines for detection, suppression and fire barriers.
• Design Engineering lead for the fire Protection Design & Installation Verification Program.  Responsible for assisting plant walkdowns of fire protection systems, punchlisting deficiencies, and confirming status of systems for client turnover.

Professional Affiliations

• American Nuclear Society (ANS) - - Member National Society; past member of Operations and & Power Division Program and Utility Working Conference Technical Program Committees; General Chair of 2002 International Topical Meeting on Probabilistic Safety Assessment (‘PSA02’); past member of the Local Sections Committee, past Chair, Vice-Chair, Treasurer, and Executive Committee member of the Michigan Section; organizer, chair, and/or panelist for national ANS meeting sessions on Process Improvement, 10 CFR 50.59 Implementation, & Design Basis Documentation
• Association of Energy Engineers - Member, Certified Energy Manager, Certified Green Building Engineer, Business Energy Professional
• Member, American Society of Quality (ASQ)
• Inducted into Tau Beta Pi and Phi Eta Sigma Engineering Honorary Societies & Phi Kappa Phi, Scholastic Honorary Society as a Penn State undergraduate

Awards And Professional Recognition

• Recipient of Penn State Outstanding Engineering Alumnus Award (2005)
• Recipient of the ANS Michigan Section "Nuclear Professional of the Year" Award (1999)
• Recipient of Bechtel Corporate Special Performance Award (1987)
• Recipient of ANS Special Committee on New Construction Certificate of Appreciation

Publications

• "Microscopic Void Characterization for Assessing Aging of Electric Cable Insulation Used in Nuclear Power Stations," D. A. Horvath, D. C. Wood, and M. J. Wylie, 2000 IEEE Conference on Electrical Insulation and Dielectric Phenomena (CEIDP)
• "Technology Tools to Capture, Search, and Maintain Your Licensing Basis," presented at the 1999 ANS Utility Working Conference session entitled "Safety Evaluations and UFSAR Updates: Walking the Fine Line Between Perfection at any Cost and Undue Regulatory Risk," August 1999
• "The Case for Infobase Technology in the Nuclear Industry," (co-author), ANS 1999 Annual Meeting Transactions, June, 1999
• "Aiding Plant Modification with Design Basis Documents," Nuclear Engineering International Magazine, May 1988
• "Controlling Design Bases Inputs to Plant Modifications," ANS International Meeting on Nuclear Power Plant Operation Transactions (TANSAO 54-Supplement 1)
• "Using Event Trees to Quantify the Effect of Post-TMI Modifications on PORV-Related LOCA Probability," ANS/ENS Topical Meeting on Probabilistic Risk Assessment Transactions, September 1981
• WCAP-9804, "Probabilistic Analysis and Operational Data in Response to NUREG-0737 Item II.K.3.2 for Westinghouse NSSS Plants," February 1981
• WCAP-9226, "Reactor Core Response to Excessive Secondary Steam Release" (Westinghouse Steamline Break Topical Report), January 1978