1. Paul D. O’Larte
2526 N 109th
Ter Apt 209 (816) 738-5003
Omaha, NE 68164 pdolarte@gmail.com
SUMMARY
Three years’ experience with pressurized water reactor core design and analysis. Technical experience
performing reactor physics, thermal hydraulics, and safety analyses. Leadership experience with small groups,
project ownership, and communication.
EDUCATION
Missouri University of Science and Technology Rolla, MO
B.S. Nuclear Engineering, Minor Mathematics Cumulative GPA: 3.42 / 4.0
Major GPA: 3.93 / 4.0
Developed a reactor kinetics model using MCNP-DSP for criticality evaluations and determined appropriate
materials for a small modular reactor as a senior design project.
PROFESSIONAL EXPERIENCE
Omaha Public Power District Omaha, NE
Nuclear Engineer I, Fort Calhoun Nuclear Power Station June 2013 – Present
Engineer in the nuclear fuels organization. Nuclear fuel assembly and reactor core design, thermal hydraulics
analysis, and support for station operations and reactor engineering organizations.
Omaha Public Power District Omaha, NE
Co-op, Fort Calhoun Nuclear Power Station May 2011 – August 2012
Engineer intern in the probabilistic risk assessment and nuclear fuels organizations. Offline work risk assessment
and time-to-boil calculations for the reactor cavity and spent fuel pool.
TECHNICAL EXPERIENCE
Leadership
 Led reload core design efforts for multiple cycles applying NRC-approved methods in core physics,
thermal hydraulics, and safety analysis. Prepared analyses to update and verify the design basis.
 Led technical task pre and post-job briefs during the development of new analyses. Established roles
and responsibilities, documented relevant operating experience, reviewed critical inputs to calculations,
and assessed human performance risks.
 Prepared risk assessments and 10CFR50.59 reviews for the reload core designs. Managed risk
associated with parameters changing outside of station and fleet operating experience.
 Benchmarked reload core design efforts through core follow analysis and in-core detector performance
monitoring.
 Prepared first-of-a-kind reports to document the reload core design using new processes, procedures,
and practices under the Exelon management model. Presented reports and schedules to station senior
leadership for approval.
 Mentored engineers in neutronics and thermal hydraulics codes, methods, and practices.
 Represented the team on the training curriculum review committee. Recommended actions to provide
key training to the engineering and nuclear fuels organizations.

2. Paul D. O’Larte
Reactor Physics Analysis
 Experienced in the application of the Studsvik Scandpower reactor physics codes INTERPIN-3,
CASMO-4, CMS-LINK, and SIMULATE-3. Modeled new nuclear fuel assembly designs to develop
fuel temperature data, cross-section lattices, core loading patterns, and depletions analyses for transient
and steady-state applications.
 Developed core loading patterns to achieve specified cycle lengths while meeting technical
specifications and vendor requirements for fuel pin peaking and exposure, fuel assembly exposure, and
temperature coefficients. Applied statistical station equipment and analytical uncertainties to determine
margin.
 Analyzed the impact of the extended outage on the reload core design. Updated the reactor physics
models using a neutronics data library containing additional isotopic data.
 Prepared scripts to extract data from files produced by reactor physics codes.
Thermal Hydraulics and Safety Analysis
 Experienced in the application of the AREVA thermal hydraulics code XCOBRA-IIIC for thermal
margin evaluations. Applied statistical methods to verify monitoring and reactor protective system
setpoints.
 Determined the impact of modified plant equipment, updated plant processes and procedures, and
updated methodology on the bounding safety analyses.
 Trained in reactor system modeling for safety analysis using the AREVA S-RELAP5 code.
Station Operations and Reactor Engineering Support
 Developed a power and temperature coastdown analysis for the permanent cessation of operation of the
station. Verified core operating limits and safety analysis limits remained bounding.
 Maintained system administration for the GARDEL core monitoring system and performed
troubleshooting activities. Prepared updates to the neutronics data libraries.
 Developed neutronics data for zero power and mid-cycle physics testing. Supported control room
personnel during testing.
 Evaluated fuel failure criteria during quarterly emergency planning drills as the technical support center
reactor engineer.
Co-op Responsibilities
 Assisted supervisor with the department budget and prepared business cases for projects.
 Assisted probabilistic risk assessment engineers with offline work risk assessments.
 Prepared heatup and time-to-boil calculations for the reactor cavity and spent fuel pool.
COMPUTER SKILLS
Scripting Languages
 Python, Perl, Ruby, C++, Unix, and Linux
Computer Software
 MCNP transport codes
 COBRA subchannel analysis codes
 RELAP accident analysis codes
 Studsvik Scandpower CASMO cross section lattice codes, SIMULATE two-group nodal codes, and
INTERPIN fuel performance codes