BRIAN W. WOODMAN
Mechanical Engineer

Extensive experience with methodology development in the area of probabilistic modeling.
Thermal-hydraulic, fuel performance, system, corrosion behavior, and Reactor Protection
System analyses. Developed stochastic simulation codes in the areas of thermal hydraulic
analysis, steam generator performance, fuel performance, and PWR neutronics. Developed
statistical sampling plans in the nuclear manufacturing area. More than 28 years experience
in the nuclear and aerospace industries both as an individual contributor and task leader.
Developed and implemented the application of predictive models for nuclear steam
generator reliability and repair.

Twenty-two years at ABB-Combustion Engineering Nuclear Services. Responsible for the
development of engineering models in the fuel performance, thermal hydraulics, and safety
areas. He has served as principal investigator on major tasks involving the application of
advanced probabilistic methods to engineering problems in setpoint analysis and corrosion
modeling.

Wide ranging technical background. A key theme of work and expertise is the development
and application of statistical and probabilistic predictive models dealing with a wide range of
physical processes.

EDUCATION AND PROFESSIONAL BACKGROUND

• BSME (Mechanical Engineering), Tufts University (1967)
• MSME (Mechanical Engineering), University of Vermont (1975)
• Member, American Nuclear Society

SELECTED REPORTS, PUBLICATIONS, AND INVITED LECTURES

Operational Assessment for the Palo Verde Unit 3 Steam Generators Based on Eddy Current Examination End of Cycle 11, October 2004, with K. Craig, APTECH Report AES 05075868-1Q-1 (October 2005).

Condition Monitoring and Operational Assessment for the St. Lucie Unit 2 Steam Generators Based on Eddy Current Examination End of Cycle 14, January 2005, with R. Cipolla and Y. Garud, APTECH Report AES 04055411-1Q-2 (August 2005).

Condition Monitoring and Operational Assessment for the St. Lucie Unit 2 Steam Generators Based on Eddy Current Examination End-of-Cycle 13, April 2003, with R. Cipolla and Y. Garud, APTECH Report AES 03024974-1Q-3 (November 2003).

Review of Eddy Current Data for Waterford, Unit 3, APTECH Report AES 03045028-1-1 (November 2003).

Condition Monitoring and Operational Assessment of Three Mile Island Unit 1 Steam Generators at Outage R14, with R. Cipolla and K. Craig, APTECH Report AES 01104524-1Q-1 (March 2002).

Condition Monitoring and Operational Assessment for the Turkey Point Unit 4 Steam Generators Based on Eddy Current Examination, End of Cycle 18, September 2000, with R. Cipolla, APTECH Report AES 00023914-1Q-5 (December 2000).

A Prototypical Evaluation of the Effects of Axial Freespan Cracking on the Structural Integrity of Once-Through Steam Generator Tubing, APTECH Report AES 98103544-1Q-1 (December 2000).

An Updated Operational Assessment and Inspection Process Evaluation for Calvert Cliffs, Unit 1, Steam Generator, with S. Brown and K. Craig, APTECH Report AES 98023308-1Q-1 (June 2000).

An Operational Assessment of Calvert Cliffs, Unit1 Steam Generators for Cycle 15, with R. Cipolla and J. Grover, APTECH Report AES 00013888-1Q-1 (June 2000).

Structural Integrity Evaluation of Axial Outside Diameter Stress Corrosion Cracking at Eggcrate Supports for Arkansas Nuclear One Unit 2 Under Severe Accident Conditions, APTECH Report AES 00033958-1-1 (April 2000).

Structural Integrity Evaluation of Axial Outside Diameter Stress Corrosion Cracking at Supports for Arkansas Nuclear One Unit 2 During Cycle 14 Post Mid-Cycle Operation, APTECH Report AES 99113855-1-1 (March 2000).

A Prototypical Evaluation of the Effects of Axial Freespan Cracking on the Structural Integrity of Once-Through Steam Generator Tubing, APTECH Report AES 98103544-1Q-1 (November 1999).

Reduced Plus Point Inspection at Calvert Cliffs Unit 1: Phase 2, with K. Craig, APTECH Report AES 99073757-1-1 (October 1999).

Modeling of Free-Span Cracking Growth Rates in ABB/CE Steam Generators, APTECH Report AES 96112906-1Q-6 (September 1999).

User's Manual for the AX97MC Program, APTECH Report AES 96112906-1Q-5 (September 1999).

An Operational Assessment for the Calvert Cliffs, Unit 2, Steam Generators, with R. Cipolla, K. Craig, and Y. Garud, APTECH Report AES 99033650-1Q-1 (July 1999).

Probability of Burst Prediction Model for Evaluation of Tube Integrity Covering Severe Accidents, with Y. Garud and R. Cipolla, APTECH Report AES 99023613-1-1 (June 1999).

Structural Integrity Evaluation of Circumferential Outside Diameter Stress Corrosion Cracking at Expansion Transitions for Arkansas Nuclear One, Unit 2 Operation During Cycle 14, with R. Cipolla and K. Craig, APTECH Report AES 99033643-1-2 (May 1999).

Operational Assessment Projections of Calvert Cliffs Unit 2 Steam Generator Tubing for Freespan Corrosion Degradation, with R. Cipolla, APTECH Report AES 98113571-1-1 (March 1999).

A Parametric Evaluation of PWSCC at Dented Supports for SONGS Unit 2, Cycle 10, with K. Craig, APTECH Report AES 98113570-1-2 (January 1999).

An Assessment of Inspection Strategy For St. Lucie, Unit 2 Steam Generators for End of Cycle 10, with K. Craig, APTECH Report AES 98063422-1-2 (November 1998).

Projected Operational Assessment of St. Lucie Power Plant, Unit 2 Steam Generators for End of Cycle 10, with K. Craig, APTECH Report AES 98063422-1-1 (October 1998).

Probabilistic Operational Assessment of Axial Corrosion Degradation at Calvert Cliffs Unit 1, APTECH Report AES 96072797-1Q-1 (November 1997).

A Probabilistic Operational Assessment of Steam Generator Tube Degradation at SONGS Unit 2 for Cycle 9, APTECH Report AES 97043057-1-1 (September 1997).

Update of Corrosion Degradation Predictions for Diablo Canyon Steam Generator Tubing, APTECH Report AES 96092860-1-1 (March 1997).

Palo Verde Unit 2 One Time Analysis Regarding the Impact of Upper Bundles Corrosion Degradation During Cycle 7, with S. Brown, APTECH Report AES 96072812-1-1 (December 1996).

Analysis of ODSCC/IGA at Tube Sheet in Tube Support Locations at St Lucie Unit 1, with S. Brown, APTECH Report AES 96052749-1-1 (October 1996).