ML19205A520
| ML19205A520 | |
| 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: ML19205A520 (5) | |
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:
NER008 John Simons Curriculum Vitae
MPR Associates, Inc.
320 King Street Alexandria, VA 22314 703-519-0200 www.mpr.com John W. Simons EXPERIENCE
SUMMARY
Mr. Simons joined MPR in 1987 and his work has focused on nuclear power plants. He has directed test programs to assess degradation of concrete due to chemical processes. He has overseen MPRs efforts on license renewal and subsequent license renewal related to concrete degradation.
Mr. Simons is currently the General Manager of Projects, with responsibility for overseeing execution of all MPR projects (Power Services, Federal Services and Product Development). He previously served as Director Plant Systems & Components and General Manager of Power Services.
ACCOMPLISHMENTS
SUMMARY
Alkali-Silica Reaction in Concrete Directed multi-year program to evaluate the impact of ASR on reinforced concrete structures at a nuclear power facility.
x The initial phase included: (1) extensive site walkdowns to document the extent of condition; (2) a limited-scope test program to assess the performance of post-installed anchors in ASR-affected concrete; (3) assessment of the impact of ASR on the adequacy of plant structures and anchors.
x The second phase included execution of large-scale test programs to assess: (1) the effect of ASR on shear strength, flexure, and reinforcement anchorage using beams without transverse reinforcement; (2) the impact of ASR on anchor capacity; and (3) evaluation of instrumentation for monitoring expansion.
x The final phase included development of a license amendment request for a change in methodology for addressing ASR and support for enhancing the Structures Monitoring Program and Aging Management Programs.
Played a key role in interfacing with the regulator throughout the 8-year effort. Developed a presentation for an all-day ACRS meeting on management of ASR.
Provided oversight of efforts for EPRI to:
x Develop a screening approach for nuclear plants to determine their susceptibility to ASR, investigate its presence and determine the extent of condition.
x Develop generic aging management guidance.
Boric Acid Attack of Concrete Directed effort to evaluate degradation of a Fuel Handling Building, a reinforced concrete structure, from prolonged exposure to boric acid from the Spent Fuel Pool. This effort included: multiple testing programs to quantify the degradation rate of concrete and embedded steel to boric acid; analytical modeling of reaction kinetics; and assessment of the structural adequacy of the building based on the postulated extent of degradation. The effort demonstrated that the building will be structurally adequate through the end of plant life, including consideration of license renewal. The effort also led to development of an aging management strategy to support license renewal.
Oversaw efforts that developed multiple EPRI reports that provide guidance for evaluating and managing the aging effects associated with leakage of borated water from PWR spent fuel pools.
LOCA Thermal-Hydraulic Testing Provided technical support for the International Program on the Thermal-Hydraulic Behavior of ECC during the Refill and Reflood Phases of a LOCA in a PWR (2D/3D Program). This effort included:
x Specification and evaluation of multiple test series at the full-scale Upper Plenum Test Facility (UPTF); and x
Preparation of reports which analyzed the test results, compared results to subscale tests and TRAC simulations, and assessed their implications for reactor safety issues.
Served as principal editor of summary reports covering 15 years of research.
John W. Simons Page 2 of 4 Engineering Leadership of Large Projects Provided engineering leadership and management on large projects at nuclear power plants. MPR developed the procurement specifications, evaluated bids, and provided the primary interface with vendors on technical and schedule issues.
MPR provided oversight of design change package preparation by the architect engineer, and resolved technical issues during installation.
x Feedwater Heater and MSR Tube Bundle Replacement. Acted as Project Engineer for replacement of six low pressure FWHs and six moisture separator reheater tube bundles. He was the primary interface with the vendor on all technical issues and a key contributor to successful negotiations with the vendor on back charges.
x Nuclear Power Plant Security Upgrades.
Directed MPR effort to provide project engineering and construction management services for a permanent checkpoint facility to satisfy the revised Design Basis Threat. The upgrades were completed by the NRCs deadline and well-received by NRC. Also, acted as Technical Lead for upgrades to ensure success in a graded Force-on-Force exercise. These upgrades were instrumental in decisive victories in the graded Force-on-Force exercise.
x Generator Step Up Transformer Replacement. Managed MPR effort to provide project engineering support for replacement of a generator step up (GSU) transformer and construction of a storage facility for spare GSU transformers. The transformer replacement was successfully completed during a 20-day outage.
CFCU Modifications Managed MPR project to simplify the portion of the Service Water system that supplies Containment Fan Cooler Units at a nuclear plant. The project reduced the required flow rate during accident conditions and adopted a single-flow for normal and accident conditions. The project also addressed silt accumulation in the system. The MPR effort included: conceptual design for the modifications; determination of the new flow to the CFCUs during accident conditions; all thermal-hydraulic analyses; and support for a license amendment request. The simplified system significantly reduced operator burden and system maintenance requirements.
Extended Power Uprates Involved with MPRs efforts related to Extended Power Uprates (EPUs), including directing several of the efforts. These efforts include the following.
x Independent assessment of scoping study, project cost estimates and project plan for the proposed EPU to support the board of directors decision to approve the EPU.
x Consulting on key decisions related to an EPU including: selection of the thermal power target, evaluation of options for implementing an EPU given uncertainty in the schedule for obtaining the necessary regulatory approvals, and the decision to defer EPU implementation.
x Engineering support for component repairs/upgrades to support an EPU:
moisture-separator upgrades; and FWH shell repairs and re-rating.
x Extent-of-Condition review to assess EPU-related vulnerabilities following the steam dryer issues.
x Independent review of vendor studies that evaluated the impact of the BWR and PWR power uprates on plant systems and components.
EPRI MOV Performance Prediction Program Coordinated preparation of the EPRI MOV Performance Prediction Program Topical Report, which summarizes the entire program and presents the thrust and torque prediction methods developed in the program. It also documents the technical justification for the program and describes the individual testing efforts performed within the program. This report is the official licensing submittal of the Program and constitutes the basis for the NRC's review of the EPRI Program.
Pressure Locking/Thermal Binding of MOVs Developed and applied an innovative method for predicting bonnet pressurization due to valve heat up which accounts for expansion of the bonnet with pressure and temperature. Predictions of the pressure increase agree favorably with test data, and are markedly less than would be predicted assuming a rigid body. This model has been applied to valves at several nuclear sites.
Performed transient heat transfer calculations to determine the change in bonnet fluid temperature due to ambient temperature transients or system temperature transients. Results of these calculations were input into calculations of bonnet pressurization using the model described above.
John W. Simons Page 3 of 4 Feedwater Heater Shell Inspection & Repair Directed MPR efforts related to feedwater heater (FWH) shell thinning.
x Provided engineering support for repair of FWH shells to address thinning in the vicinity of the steam inlet nozzles. Repairs restored the heater shell to compliance with the ASME Code and modified heater internals to mitigate future thinning.
x Developed minimum wall thickness criteria for interim operation of FWHs with thinned shells.
The criteria maintain ASME Code margins for internal and external pressure for general and localized thinning.
x Developed an improved replacement shell section design (clad shell section with clad steam nozzle) to provide a permanent solution to shell thinning at the steam inlet nozzle.
Provided engineering support for fabrication and installation of the replacement shell sections.
x Managed MPR project for engineering support for re-rate and repair of FWH shells. This project included: design/specification of replacement shell sections and external shell stiffeners, engineering support during fabrication, ASME Code design report for the re-rate/repairs, definition of code compliance approach (ASME Code, NBIC, state regulations), contingency planning, consulting on DCP development, and on-site support during installation. The project covered 24 FWHs (36 steam inlet nozzles).
Circulating Water Intake Improvements Directed MPRs efforts to evaluate alternatives for seasonal reduction in Circulating Water System flow to reduce ingress of detritus into the plant.
The MPR scope included evaluation of alternatives, quantification of the improvement in net electrical output of the plant, and development of a conceptual design for using variable frequency drives.
Participated in the definition of an overall integrated strategy for improvements to address grassing by reducing flow, replacing traveling and relocating the detritus return. This included scoring of different combinations of options to determine the best approach.
Feedwater Heater Support Provided engineering support for FWH-related problems at coal-fired and nuclear power plants.
Selected tasks are identified below.
x Post-mortem on Failed Heaters. These efforts included inspection of disassembled heaters and on-site supervision of heater disassembly. Recommendations for how to avoid similar failures in other heaters were provided.
x Heater Replacement Evaluations. Assessed current condition of heaters, projected future condition, and established schedule for heater replacements. This work also involved identification of options for addressing continued degradation of the heaters and assessing the impact of the options on feedwater system operation and overall plant capacity.
x Nondestructive Examination (NDE).
Provided engineering support for NDE of tubes in high-pressure FWHs at supercritical fossil stations. This work involved determination of NDE scope, interpretation of NDE results, and recommendation of tubes to be plugged. This task reduced loss-of-generation due to FWH tube leaks by identifying seriously damaged tubes and plugging them before they fail in service.
x Insurance Claims for Feedwater Heaters.
Supported plant in successful insurance claims for feedwater heaters. This effort included development of the technical basis for the claim, and quantification of the monetary value of the damages.
Tritium Leakage Task Force Participated on a task force at a commercial nuclear power plant to determine the source of tritium leakage from high concentration plant sources to the external environment.
Buried Pipe Inspections Directed MPR efforts in support of inspection of buried prestressed concrete cylinder pipe (PCCP) at a nuclear power plant. These efforts included (1) development of acceptance criteria for the inspections, (2) analyses to demonstrate that the as-found condition of flawed bell-and-spigot joints was suitable for continued service, and (3) development of contingency repair designs.
John W. Simons Page 4 of 4 EDUCATION University of Maryland, B.S., Chemical Engineering, 1987 Columbia Union College, B.S., Chemistry, 1986 PUBLICATIONS EPRI Reports EPRI MOV Performance Prediction Program: Topical Report. EPRI, Palo Alto, CA: 1994. TR-103237.
Program on Technology Innovation: Approach to Transition Nuclear Power Plants to Flexible Power Operations. EPRI, Palo Alto, CA: 2014. 3002002612.
Aging Management for Leaking Spent Fuel Pools. EPRI, Palo Alto, CA: 2016. 3002007348.
Welding and Repair Technology Center: Boric Acid Attack of Concrete and Reinforcing Steel in PWR Fuel Handling Buildings. EPRI, Palo Alto, CA: 2012. 1025166.
Best Practices for Evaluation of Spent Fuel Pool Leakage in Pressurized Water Reactors, included as an appendix to: Advanced Electromagnetic Inspection Methods for Fuel Pool and Transfer Canal Liners. EPRI, Palo Alto, CA: 2012. 1025214.
Tools for Early Detection of ASR in Concrete Structures. EPRI, Palo Alto, CA: 2015. 3002005389.
Papers and Presentations White, P., S. Bernhoft, A. Roberts, J. Simons, An Approach for Migrating Nuclear Power Plants to Flexible Power Operations, Proceedings of the 9th Nuclear Plants Current Issues Symposium, pp. VII 3/1 to VII 3/14.
Simons, J., R. Noble, C. Bagley, J. Moroney and R. Vayda, Approach for Large-Scale Testing of Concrete Affected by Alkali-Silica Reaction, Proceedings of the 9th Nuclear Plants Current Issues Symposium, pp. VIII-3/1 to VIII-3/21.
Noble, R. and J. Simons, ASR in Reinforced Concrete Structures: A Comprehensive Program to Address ASR at Seabrook, EPRI Symposium on Concrete Structures, Liner Barriers and Tanks, May 6 8, 2014.
Simons, J., C. Bagley and R. Vayda, Nuclear Power Plant Concrete Aging Management Issues, Proceedings of the 8th Nuclear Plants Current Issues Symposium, pp. VII-4/1 to VII-4/20.
Antoniazzi, A. and J. Simons, Case Studies on Tritium Pathways, EPRI Buried Pipe Integrity Group Meeting, February 15-17, 2011.
Simons, J., Generic Approach for Assessing Impact of SFP Leakage on Reinforced Concrete Structures, 2nd EPRI Fuel Pool, Transfer Canal, and Concrete Degradation Issues Workshop, May 11-13, 2010.
Simons, J. and R. Keating, Managing Feedwater Heater Shell Thinning, 10th International Conference on Nuclear Engineering, April 2002.
Bradley, M., J. Simons, D. Strawson and D. Chapin, Overview of Dry Storage of Spent Nuclear Fuel in the U.S., Seventh International Conference on Nuclear Engineering, April 1999.
Claude, E.J., H. Nakamura, D.M. Chapin, J.W. Simons and H. Seneviratne, Update on Decommissioning Waste from Nuclear Power Plants, 7th International Conference on Nuclear Engineering, April 1999.
Damerell, P.S., D.H. Harrison, P.W. Hayes, J.W. Simons, and T.A. Walker, "Effects of Pressure and Temperature on Gate Valve Unwedging," Fourth NRC/ASME Symposium on Pump and Valve Testing, NUREG/CP-0152, pp. 3C-49 to 3C-71.
Rhee, G., P. Damerell and J. Simons, "Use of 2D/3D Data to Scale Up Liquid Carryover/De-entrainment (Steam Binding) Phenomena to a PWR," 16th Water Reactor Safety Information Meeting, October 24-27, 1988.
NUREGs Damerell, P.S., and J.W. Simons, editors, 2D/3D Program Work Summary Report, edited by MPR Associates, NUREG/IA-0126, June, 1993.
Damerell, P.S., and J.W. Simons, editors, Reactor Safety Issues Resolved by the 2D/3D Program, edited by MPR Associates, NUREG/IA-0127, July, 1993.