ML19205A521
| ML19205A521 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/24/2019 |
| From: | Morgan, Morgan, Lewis & Bockius, LLP, NextEra Energy Seabrook |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| 50-443-LA-2, ASLBP 17-953-02-LA-BD01, RAS 55113 | |
| Download: ML19205A521 (4) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD In the Matter of NEXTERA ENERGY SEABROOK, LLC (Seabrook Station, Unit 1)
Docket No. 50-443-LA-2 ASLBP No. 17-953-02-LA-BD01 Hearing Exhibit Exhibit Number:
Exhibit
Title:
NER009 Chris Bagley Curriculum Vitae
MPR Associates, Inc.
320 King Street Alexandria, VA 22314 703-519-0200 www.mpr.com Christopher W. Bagley EXPERIENCE
SUMMARY
2009 - Present MPR Associates, Inc.
2004 - 2009 United States Navy Since joining MPR in 2009, Mr. Bagley has been involved in a variety of projects for the nuclear industry and the federal government as the technical lead and/or project manager. His focus has been with plant systems, structures, and components and includes work on a wide range of areas including modifications to upgrade plant systems, implementation of new requirements imposed on nuclear power plants resulting from the events at Fukushima-Daiichi, evaluation of concrete degradation mechanisms, and general materials and water chemistry issues.
ACCOMPLISHMENTS
SUMMARY
Concrete Degradation by Alkali-Silica Reaction Technical lead for numerous efforts involving potential concrete degradation by alkali-silica reaction (ASR) at Seabrook Station and implications for license renewal. Specific accomplishments include the following:
x Performed inspections of concrete surfaces affected by ASR as part of an initial assessment of the extent of condition.
x Developed technical content and provided technical and quality oversight for test programs performed at a university to gather information necessary for technical evaluation at the plant.
x Prepared several reports for submittal to the NRC describing the test programs and using the results of the programs to support evaluations at the plant, including:
o Description of test programs, objectives, and basis for application of results at plant o Report of results for embedded anchor performance testing in concrete affected by ASR.
o Description of a novel approach for determining ASR in concrete since original construction o Overview of all test programs (shear, reinforcement anchorage, instrumentation, embedded anchor), their results, and implications for aging management at the plant x
Prepared responses to several NRC Requests for Additional Information and supported on-site audits, including direct engagement with NRC Staff Led project for EPRI to develop a screening approach for nuclear plants to determine their susceptibility to ASR, investigate its presence, and determine the extent of condition. This approach was published in an EPRI report.
Led project for EPRI to develop aging management guidance for plants with concrete that has been affected by ASR. This guidance was published in an EPRI report.
Concrete Degradation by Acid Attack Evaluated potential degradation of reinforced concrete structures from prolonged exposure to boric acid at several commercial nuclear stations to address NRC concerns about adequacy of the structures and implications for license renewal.
Evaluations consisted of integrating plant data with experimental results of test programs conducted by MPR and information available in scientific literature to reach conservative conclusions on potential for degradation.
Recommended options for addressing potential degradation including concrete sampling and evaluation methods, leakage detection techniques, and liner repair options.
Follow-up effort included oversight of concrete coring and assessment of core examination results to support degradation projections from initial evaluation.
Authored two reports for EPRI on this topic.
Christopher W. Bagley Page 2 of 3 Fukushima Lessons Learned - Diverse and Flexible (FLEX) Coping Strategies Reviewed FLEX strategies and corresponding NRC submittals for 10+ nuclear stations representing multiple utilities.
Recommendations to optimize strategies resulted in savings of over $25M.
Developed approach for establishing a FLEX Program and developed template for FLEX Program Document that was distributed by the Nuclear Energy Institute to all U.S. nuclear power plants for use in establishing a FLEX program.
Prepared the FLEX Final Integrated Plan for several nuclear plants. These NRC submittals describe the FLEX strategy and are the primary basis for the NRC Staff Assessment of compliance with the NRC order to develop mitigating strategies.
Prepared assessments of FLEX strategies against re-evaluated flooding hazards (i.e.,
Mitigating Strategies Assessments) at several nuclear power plants. These NRC submittals are the primary basis for the NRC Staff Assessment of compliance with direction to the impact of the re-evaluated flood hazard on the FLEX strategy.
Piping Modification Design Led project to develop and implement a solution to modify buried piping at a nuclear power station to facilitate compliance with requirements internal inspections.
This project included an alternatives analysis that considered implications for hydraulic performance, heat transfer capability, licensing, constructability, maintainability, and industry best practices. In addition, a net present cost model was prepared to evaluate the capital costs and future maintenance costs of various options. The recommended solution included a new branch of corrosion-resistant piping that included components to support inspections, such as a valve, an access hatch, and tornado missile protection. Developed the conceptual design for the overall modification, and led efforts to support detailed design for the piping bell-and-spigot joints, which are essential for the plants design basis.
Led MPR efforts to develop a unique design for supports for safety-related buried piping during implementation of the modification. This effort included close coordination with field personnel responsible for implementation to rapidly resolve unexpected issues that arose during installation.
Selective Leaching Led MPR projects to evaluate results of examinations of components for selective leaching. Evaluations were performed on piping, valves, and other components of several different materials.
These efforts included development of a methodology for evaluating the acceptability of components exhibiting selective leaching and projecting acceptability of comparable components in the future.
Component Modification Design Led project to develop and implement a solution for corrosion of a Moisture Separator Reheater (MSR) at a nuclear power plant.
This project included an alternatives analysis to evaluate the degradation mechanism and identify appropriate solutions. The recommended solution included a set of modifications ranging from weld overlay to replacement of internal components.
Developed a detailed design that included associated specifications, calculations, drawings, and criteria for selecting an appropriate modification for given as-found conditions.
Led MPR follow-on efforts to provide continuous on-site support during installation.
Instrumentation Modification Design Led project for EPRI to develop Common Design Packages (CDPs) for implementation of vibration sensors and a plant network at commercial nuclear power stations. These packages use the Standard Design Process approach adopted by the nuclear industry to streamline implementation of similar modifications across multiple sites.
For each CDP, this project included development of specifications, design evaluations, drawings, and calculations. The CDP contents are published in an EPRI Report.
(See Publications Summary)
Christopher W. Bagley Page 3 of 3 EDUCATION Masters of Engineering Management; Old Dominion University, Norfolk, VA; 2007 Naval Nuclear Propulsion Plant and Reactor Core Design Training; U.S. Navy, Bettis Reactor Engineering School, Pittsburgh, PA; 2005 Bachelor of Science, Chemical Engineering; University of Virginia, Charlottesville, VA; 2004 PUBLICATIONS EPRI Report 3002011820, Online Monitoring - Engineering Change Package Content for a Distributed Antenna System and Wireless Vibration Sensors, April 2018.
EPRI Report 3002010093, Long-Term Operations: Aging Management of Alkali-Silica Reaction Affected Structures, December 2017.
EPRI Report 3002007348, Aging Management for Leaking Spent Fuel Pools, December 2016.
EPRI Report 3002005389, Tools for Early Detection of ASR in Concrete Structures, September 2015.
EPRI Report 1025214 (Appendix), Best Practices for Evaluation of Spent Fuel Pool Leakage in Pressurized Water Reactors, July 2012.
EPRI Report 1025166, Welding & Repair Technology Center: Boric Acid Attack of Concrete and Reinforcing Steel in PWR Fuel Handling Buildings, May 2012.