ML13135A231

Beaver Valley, Unit 1 - Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications

ML13135A231
Person / Time
Site:	Beaver Valley
Issue date:	10/23/2012
From:	ABS Consulting
To:	Office of Nuclear Reactor Regulation, FirstEnergy Nuclear Operating Co
Shared Package
ML131350549	List: L-13-118, Resubmittal of FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima. ML13135A229 ML13135A230 ML13135A231 ML13135A233 ML13135A234 ML13135A235 ML13135A236 ML13135A237 ML13135A238 ML13135A240 ML13135A241 ML13135A242 ML13135A243 ML13135A244 ML13135A245 ML13135A246 ML13135A247 ML13135A248 ML13135A249 ML13135A251
References
L-13-118, TAC MF0092, TAC MF0093, TAC MF0116, TAC MF0159
Download: ML13135A231 (37)

Text

{{#Wiki_filter:RE s uM " t iffi"i'3iifi ,.o r I oNS 279 Dorchester Rd, Akron Ohio 44313 Phone 234-678-8262 E-mail jreddman@aol.com JOHNE. REDDINGTON Workexperience January 2OO7 to present: Principal Consultant, Probabilistic Risk Analysis: Lead fire PRAfor the Davis-Besse fire PRA, including contractor oversight and coordination; specialization in H RA, including operations interface,model integration, dependency analysis and PWROG HRA Subcommittee; fire PRA peer reviews; currently technical lead for seismic PRA for FENOC fleet; mentor to junior and co-op engineers. August 2oo4- January 2oo7:Principal Programs Engineer, Fleet office Akron, OH: responsiblefor the fire protection program for the FENOC fleetAugust 2oo3 to August 2oo4: Davis-Besse Nuclear Station Oak Harbor, OHTraining Manager: Responsible for direction and implementation ofsite's accredited training programs. Heavily involved with high intensitytraining required to get Davis-Besse back on line following a two year outage replacing the reactor head. January 2oo1 to August 2oo3 : Davis-Besse Nuclear Station OakHarbor, OH Supervisor Quality Assurance Oversight for Maintenance:Responsible for value added assessments based on performance aswell as compliance. Ensure industry best practices are used as standards for performance in maintenance, outage planning, and scheduling. Lg96 to January 2oo1, Superintendent Mechanical MaintenanceManage the short and long term direction of the Mechanical and Services Maintenance Departments. Responsible for Bo to 90 person department with a budget between 7 and 15 million dollars a year. Direct the planning,engineering, and field maintenance activities. Direct oversight of outage preparations and implementation. One year assignment working wittlTechnical Skills Training preparing for accreditation. A-2 L993 - tgg6 Shift Manager Act as the on-shift representative of the Plant Manager. Responsible for providing continuous management support for all Station activities to ensuresafe and efficient plant operation. Establish short term objectives for plantcontrol and provide recommendations to the Shift Supervisor. Monitor core reactivity and thermal hydraulic performance, containment isolation capabilrty, and plant radiological conditions during transients and advise the operating crew on the actions required to maintain adequate shutdownmargin, core cooling capability, and minimize radiological releases.LggL - L993Senior System and Maintenance EngineerProvide Operations with system specific technical expertise. Responsible formaintaining and optimizing the extraction steam and feedwater heaters, the fuel handling equipment and all station cranes.Acted as Fuel Handling Director during refueling outages.Responsibilities Included maintaining the safe and analyzed coreconfiguration, directing operation personnel on fuel moves, directing maintenance personnel on equipment repair and preventative maintenance. 1986 - LggL Senior Design Engineer and Senior Reactor Operator student Activities included modification design work and plant representative on the Seismic Qualification Utilities Group and the Seismic Issues subcommittee. Licensed as a Senior Reactor Operator following extensive classroom, simulator, shift training, and Nuclear Regulatory Commission examination. L9B4- 1986Sargent & Lundy Engineers Chicago, IL Senior Starctrral EngineerResponsible for a design team of engineers for the steel design and layout tosupport the addition of three baghouses on a coal fired plant in Texas.Investigated and prepared both remedial and long term solutions to structural problems associated with a hot side precipitator. r98o - rg&4 Structrral EngineerResponsible for steel and concrete design and analysis for taSalle and Fermi Nuclear Power plants. Performed vibrational load and stability analysis for numerous piping systems. Member of the on-site team of engineersresponsible for timely in-place modifications to the plant structure at LaSalle.l979 - r98o Wagner Martin Mechanical Contractors Richmond, IN Engineer/ Proj ect M anagerResponsible for sprinHer system design through approval by appropriate undenffiiter. Estimator and Project Manager on numerous mechanical projects up to r.8 million dollars. A-3 Education Pnofessional memberships Other L975 - 1979Purdue Universitv West Lafayette, INBachelor of Science in Civil Engineering1990- L995University of Cincinnati Cincinnati, OHMaster of Science in Nuclear EngineeringProfessional Engineer, State of Illinois , L9B4Professional Engineer, State of Ohio, 1986 Senior Reactor Operator, Davis-Besse Nuclear Power Plant, L99o.Qualified Lead Auditor, 2oo3 SQUG qualified rgBZCommittee Chairman, Young Life Toledo Southside, Lake Erie West RegionSunday School Teacher- College age young people. ABSGonsultingAN ABS GROUP COMPANY DONALD J. WAKEFIELDDONALD J. WAKEFIELD PROFESSIONAL HISTORYABSG Consulting Inc., Irvine, California Senior Consultant, Operational Risk and Performance Consulting,2000-Present E QE International, Senior Consulta nt, 1997 -2000 PLG, Inc., Irvine, California, Senior Consultant, 1983-1997 AJgno Energy Seruices, Associate ,1981,-1983 Gener al Atomic Comp any, Enginee r, 197 4-198'1. PROFESSIONAL

SUMMARY

Mr. Donald J. Wakefield has more than 30 years experience in all phases of the risk analysis ofnuclear power plants and other complex facilities, includirg human reliability analysis. He has served as principal investigator and project manager for the risk assessment of several nuclear plants in the United States and the Far East. He served as a key risk analyst on assessments of afloating, production, offloading and storage facility (FPSO),

• oil tanker, and for the handlingof abandoned chemical weapons in China. Mr. Wakefield is also Project Manager for thedevelopment of ABS Consulting's RISKMAN@

software for risk assessment applications. He is now serving as the Chairman of the Low Power and Shutdown PRA Standard Writing Group(ANS 58.22) and serves on the ASME's Committee on Nuclear Risk Management (CNRM) and ANS's RISC Committee.PROFESSIONAL EXPERIENCEIn late 2A06, Mr. Wakefield became the writing group chairman for the ANS PRA standard for Low Power and Shutdown Events (ANS-58.22). This standard is still in development. Mr.Wakefield has also been active recently in the modeling of shutdown events. He recentlyperformed a review of the Seabrook Station, all power modes PRA model. He recently performed a Level 2 analysis for shutdown events of the KKG plant in Switzerland. These efforts are in addition to his past Level L shutdown studies for HIFAR in Austr aha, Takahama-3 / 4, and for other plants in Japan.Mr. Wakefield recently served as the principle investigator for a fire risk analysis of the WattsBar unit 2 plant to satisfy its FIVE licensing requirement. This study was performed using CAFTA.A-5 ABSGonsultingAN ABS GROUP COMPANY DONALD J. WAKEFIELD Mr. Wakefield has also performed human reliability analysis for nuclear plants. He served astask leader for the human factors analysis of the Three Mile Island (TMD Unit L PSA.Performed the original human factors analysis for the PSA and thery nearly 20 years later, worked with the plant safety staff to update the analysis using the EPRI HRA Calculator. More recently, Mr. Wakefield served as an independent reviewer for the South Texas Project upgrade to the latest EPRI HRA Calculator, and for a similar review effort for PG&E. Mr. Wakefield was co-author of the Electric Power Research Institute (EPRI) report on the SHARP-L approach to HRA analyses for PSAs.Mr. Wakefield served as principal investigator for the Beaver Valley Units 1, eind 2 PSAperformed to satisfy U.S. Nuclear Regulatory Commission (USNRC) IPE and IPE for externalevent (IPEEE) requirements.Mr. Wakefield also provided expertise in developing and analyzrng the Sequoyah and WatLsBar PSA plant models to satisfy the individual plant examination (IPE).Mr. Wakefield served as project manager for the Salem PSA update and as technical consultant for a PSA of the new production (i.e., weapons materials) modular gas-cooled reactor.Mr. Wakefield was a key contributor to accident sequence modeling, including human factorsanalysis, and seismic analysis for the Diablo Canyon PSA.Mr. Wakefield served as principal investigator in charge of extending a fault tree linking PSA plant model for a pressurized water reactor in the Far East to accommodate the assessment of plant internal fires and seismic events. Mr. Wakefield served as consultant speciabzing in accident sequence modeling and plantsystems analysis for probabilistic safety assessments (PSA). Recently, he served as technical advisor and sequence model architect for a risk assessment model for the excavation and disposal of abandoned chemical weapons in China. The study considered weapon handling errors, plant fires and weapon explosions there from. This assessment looked at all initiating events and the sequence development extended to payouts resulting from worker and population exposures, building and equipment losses and from environmental cleanup costs.Mr. Wakefield served as the technical lead and coordinated inputs from the Knoxville, SanAntonio, and Irvine offices for use by the ABS Tokyo office. Mr. Wakefield served as senior analyst for the development of a QRA model for a Floating,Productioru offloading and Storage (FPSO) facility hypothetically located in the Gulf of Mexico.This model, funded internally by ABS, looked at risk to the workers from pool fires and jet fires and environmental damage from potential oil spills. Also, in 1995, he performed riskassessment portion of an explosion analysis for the Agbami FPSO owned by Star Deep WaterPetroleum Limited, and one for the GX Platform owned by Exxon Mobil for MustangEngineering. He also served as advisor for the PSA of a new, double-hulled oil tanker.Mr. Wakefield developed the CAFTA-based accident sequence model for a seismic marginsassessment for the ACR-700 design for AECL.A-6 ABSGonsultingAN ABS GBOUP COMPANYDONALD J. WAKEFIELDMr. Wakefield served as instructor for numerous PSA courses and provided extensive utilitytraining sessions both in the U.S. and abroad. He served as course instructor to the US Nuclear Regulatory Commission for the risk assessment of external events and to describe the largeevent tree approach to sequence modeling.Mr. Wakefield provides technical direction and project management for the development of ABS Consulting's RISKMAN@ PSA software and administers the RISKMAN@ TechnologyGroup (a utility users' group). This user's group, now in its eighteenth year, funds the maintenance and development of RISKMAN@ upgrades. Mr. Wakefield provides the interfacebetween the user's group members, and the RISKMAN@ development team.Mr. Wakefield was a substantial contributor to a 5-year high temperature gas-cooled reactor (HTGR) risk assessment study. He developed numerous improvements to severe accident consequence computer programs for the HTGR. Quantified uncertainties in severe accidentsource terms and dose assessment for the HTGR, the first such assessment ever accomplished for any reactor type. Developed a procedure for prionltzing HTGR safety research programsusing PSA and formulated an initial set of research reconunendations. Prepared test specifications to implement research reconunendations.Mr. Wakefield has authored numerous scientific papers on the subject of probabilistic risk assessment methods including such topics as importance measures, comparison between eventtree and fault tree linking, and human reliability analysis techniques. EDUCATION M.S., Nuclear Engineering, University of Califomia, Berketey,l974B.S., Engineering Mathematics, University of California, Berkel ey, 1973, with highest honors MEMBERSHIPSLICENSESAND HONORS American Nuclear SocietyPhi Beta Kappa, National Scholastic Honor Society Tau Beta Pi, National Engineering Honor SocietyRegents Fellowship, University of California, 1974 Department of Engineering Certificate Awar d,'1.973SELECTED PUBLICATIONS Wakefield,D.I., and Y. Xiong, "Importance Measures Computed in RISKMANo for Windows," PSAM 5, Sth Internationnl Conference on Probabilistic Safety Assessment and Management,November 2000. ]ohnson, D. H., D. I. Wakefield, and R. Cameron, "lJse of PSA in Risk Management at aResearch Reactor," presented at the American Nuclear Society, International Topical Meeting on Probahilistic Safety Assessment (PSA'99), Washington, D.C., August22-25,1999. Quilici, M., W. T. Loh, and D.

l. Wakefield, "IPEEE Reports Survey," prepared for ComputerSofttoare Deaelopntent Co., Ltd., Tokyo, lapnn, PLG-1194, March 1998.A-7 ABSGonsultingAN ABS GROUP COMPANY DONALD J. WAKEFIELD Wakefield, D. I., "PSA and RISKMAN@ Software Training Course," presented to TennesseeV alley Authority, N etop or t B e ach, California, PLG-LI 95, February 2-6, 1998 .Wakefield, D. ]., and D. H.

johnson, "A Level L+ Probabilistic Safety Assessment of the HighFlux Australian Reactor," prepared for Department of Industry, Science and Tourism, Canberra,Austr alia, PLG-1200, ]anu ary 1998.Wakefield, D. J., and D. H. johnsory "summary Report - A Level L+ Probabilistic SafetyAssessment of the High Flux Australian Reactor," prepared for Department of Industry, Science and Tourism, Cnnberra, Australia, PLG-1201, January 1998.Wakefield, D. j., and D. H. Johnson, "Technical Summary Report - A Level 1+ Probabilistic Safety Assessment of the High Flux Australian Reactor," prepared for Department of Industry,S cience an d T ouri sm, Canberr n, Au str slia, PLG-1202, I anuary 1998 .Wakefield, D. I., M. A. Emerson, K. N. Fleming, and S. A. Epstein, "RISKMAN@ A System for PSA," Proceedirgr, Probabilistic Safety Assessment Internntional Topical Meeting, Cleantrater, Florida,pp . 722-7 29, J anuary 1993.Wakefield, D. I., R. K. Deremer, and K. N. Fleming, "Accident Management Insights Obtained During the Beaver Valley Unit 2 Individual Plant Examination Procesg " Proceedings,Probabilistic Safety Assessment lnternational Topical Meeting, Clearrttater, Florida, pp.1'049-L053, january 1993.Contributing Author t o : "sequoyah Nuclear Plant Unit 1 Probabilistic Risk Assessment Individual Plant Examination,"PLG, Inc., prepared for Tennesree Valley Authorih1,1992."Watts Bar Nuclear Plant Unit 1 Probabilistic Risk Assessment Individual Plant Examination'," PLG, Inc., prepared for Tennessee Valley Authorit11,1992. Wakefield, D.J. and S.A. Nass, "Application of RISKMAN 2.0 to the Beaver Valley PowerStation IPE," Probabilistic Snfety Assessrnent and Management Conference, Beaerly Hills, California,February 1991,. Read, I.W., and D.l. Wakefield, "Diesel Generator Technical Specification Study for Indian Point 3," PLG,Inc., prepared for Nezu York Potuer Authority, PLG-0690, December L989.Wakefield, D.I., K.N. Fleming, et al., "Beaver Valley Unit 2Probabilistic Risk Assessment," PLG,Inc., prepared for Duquesne Light Company, December 1989.Wakefield, D.J., H.F. Perla, D.C. Bley, and B.D. Smith, "Enhanced Seismic Risk Assessment ofthe Diablo Canyon Power Plant," Transactions of the Tenth International Conference on StructuralMechanics in Reactor Technology, Los Angeles, August 1989.Wakefield,D]., H.F. Perla, et al., "seismic and Fire Probabilistic Risk Assessment for a Typical japanese Planf" PLG, Inc., prepared for Mitsubishi Atomic Pozuer Industries, Inc., February 1988.Wakefield, D.J., "Three Mile Island Unit L Probabilistic Risk Assessment," PLG, Inc., prepared for GPU Nuclear Corporatiotr, November 1987. ABSGonsultingAN ABS GBOUP COMPANY DONALD J. WAKEFIELDWakefield, D.1., and C.D. Adams, "Quantification of Dynamic Hum*u:t Errors in the TMI-1PRA," International Topical Conference on Probabilistic Safety Assessment and RiskManagement, Zutrch, Switzerland, Septemb er 1987 .Fray, R.R., B.D. Smith, R.G. Berger, M.L. Miller, H.F. Perla, D.C. Bley, D.]. Wakefield, and l.C.Lirt, "Probabilistic Risk Assessment for Pacific Gas and Electric Company's Diablo CanyonPower Plant," presented at the International Conference on Radiation Dosimetry and Safety, Taipei, Taittran, March 1987 .Wakefield, D.I., A. Singh, et al., "systematic Human Action Reliability Procedures (SHARP)Enhancement Projecf SHARP1 Methodology Repor!" PLG, Inc., prepared for Electric PoztterRe search Institute, 1987 .Wakefield, D.I., "Salem Nuclear Generating Station Reliability and Safety ManagementProgram: Baseline Safety Assessment," PLG, Inc., prepared for Public Seraice Electric and Gas Company,Iuly 1986.Wakefield, D.1., "PRA Procedures for Dependent Events Analysis, Volume II, Systems LevelAnalysis," PLG,Inc., prepared tor Electric Poruer Research Institufe, December 1985.PLG, Inc., "Application of PRA Methods to the Systems Interaction Issue," prepared for Electric P out er Re se ar ch ln s titute, PLG-0284, April 198 4.Wakefield, D.I., D.C. Iden, and G. Paras, "Oyster Creek Conceptual HPCI System Risk Reduction Study," prepared for GPUNuclear Corporation,PLG,Inc., PLG-0308, December L983.Wakefield, D.1., R.K. Deremer, et al., "Probabilistic Risk Assessment and Systems InteractionAnalysis Reference Manual," Cygna Energy Services Report to Texas Utilities, October 1982.Wakefield, D.1., and D. Ligor; "Quantification of Uncertainties in Risk Assessment Using the STADIC Code," Internationnl Anrcrican Nuclear Society/European Nuclear Society Topical Meeting on Probabilistic Risk Assessment, Port Chestur, Nezp York, September 20-24,1981.Fleming, K.N., D.j. Wakefield, et al., "HTGR Accident Initiation and Progression AnalysesPhase II Risk Assessment," t-lnited States Depnrtment of Energy Report, GA-A15000, UC-77, April 1978 A-9 ABSGonsulting AN ABS GROUP COMPANYFARZIN R. BEIGI, P.E. PROFESSIONAL HISTORYABSG Consulting Inc,, Oakland, CaliforniaSenior Consult ant, 2004-PresentTechnical Manag er, 200'1.-2004EQE International, Principal Engine er, 1990-2001 TENERA L.P, Berkeley, California, Project Mana ger, 1982-1990PROFES S IONAL EXPERIENCE Mr. Beigi has more than 29 years of professional structural and civil engineering experience. Asa Senior Consultant for ABS Consulting, Mr. Beigi provides project management and structuralengineering services, primarily for seismic evaluation projects. He has extensive experience inthe areas of seismic evaluation of structures, equipment, piping, seismic criteria development,and structural analysis and design. Selected project accomplishments include the following:. Most recently, Mr. Beigi has been involved in perfor*i^g seismic fuagplity analysis ofequipment and structures at Gosgen Nuclear Power Plant in Switzerland, Lungmen NuclearPower Plant in Taiwan, Oconee Nuclear station in U.S., Point Lepreau Nuclear Plant inCanada, Beznau Nuclear Power Plant in Switzerland, Olkiluoto Nuclear Power Plant in Finland, and Neckarwestheim Nuclear Power Station in Germany. o Provided new MOV seismic qualification (weak link) reports, for North Anna, Surry andKewaunee nuclear plants to maximize the valve structural thrust capacity by eliminatingconservatisms found in existing qualification reports and previously used criteria.o At Salem Nuclear Power Plant Mr. Beigi developed design verification criteria for seismic adequacy of HVAC duct systems. He also performed field verification of as-installed HVAC systems and provided engineering evaluations documenting seismic adequacy ofthese systems, which included dynamic analyses of selected worst-case bounding samples.. Mr. Beigi has participated in several piping adequacy verification programs for nuclearpower plants. At Watts Bar and Bellefonte Nuclear Plants, he was involved in thedevelopment of walkdown and evaluation criteria for seismic evaluation of small borepiping and participated in plant walkdowns and performed piping stress analyses. AtOconee Nuclear Station, Mr. Beigi was involved in developing screening and evaluationcriteria for seismic adequacy verification of service water piping system and performed walkdown evaluations, as well as, piping stress analyses. At Browns Ferry Nuclear Plant, Mr. Beigi was involved in the assessment of seismic interaction evaluation program for largeand small bore piping systems. A-10 ABSGonsultingAN ABS GROUP COMPANY FARZIN R. BEIGI, P.E.. Mr. Beigi performed a study for the structural adequacy of bridge cranes at DOE's PaducahGaseous Diffusion Plant utilizing Drain-2DX non-linear structural program. The study focused on the vulnerabilities of these cranes as demonstrated in the past earthquakes. o Mr. Beigi has generated simplified models of structures for facilities at Los Alamos NationalLab and Cooper Nuclear Station for use in development of building response spectraconsidering the effects of soil-structure-interactions.. Mr. Beigi has participated as a Seismic Capabitity Engineer in resolution of the US NRC's Unresolved Safety Issue A-46 (i."., Seismic Qualification of Equipment) and has performed Seismic Margin Assessment at the Browns Ferry Nuclear Power Plant (TVA), OconeeNuclear Plant (Duke Power Co.), Duane Arnold Energy Center (Iowa Electric Company), Calvert Cliffs Nuclear Power Plant (Baltimore Gas and Electric), Robinson Nuclear PowerPlant (Carolina Power & LighQ, and Bruce Power Plant (British Energy - Ontario, Canada).He has performed extensive fragility studies of the equipment and components in the switchyard at the Oconee Nuclear Power Plant.. Mr. Beigi has developed standards for design of distributive systems to be utilized in the new generation of Light Water Reactor (LWR) power plants. These standards are based onthe seismic experience database, testing results, and analytical methods.. Mr. Beigi managed EQE's on-site office at the Tennessee Valley Authority Watts Bar Nuclear Power Plant. His responsibilities included staff supervision and technical oversightfor closure of seismic systems interaction issues in support of the Watts Bar start-upschedule. Interaction issues that related to qualification for Category I piping systems and other plant features included seismic and thermal proximity issues, structural failure and falling of non-seismic Category I commodities, flexibility of piping systems crossing between adjacent building structures, and seismic-induced spray and flooding concems.Mr. Beigi utilized seismic experience data coupled with analytical methods to address theseseismic issues.. As a principal engineer, Mr. Beigi conducted the seismic qualification of electrical raceway supports at the Watts Bar Plant. The qualification method involved in-plant walkdownscreening evaluations and bounding analysis of critical case samples. The acceptancecriteria for the bounding analyses utilized ductility-based criteria to ensure consistentdesign margins. Mr. Beigi also provided conceptual design modifications and assisted inthe assessment of the constructability of these modifications. Mr. Beigi utilized similarmethods for qualification of HVAC ducts and supports at Watts Bar, and assisted criteria and procedures development for HVAC ducting, cable trays, conduit and supports at theTVA Bellefonte nuclear power plant. Mr. Beigi also has extensive experience utili zng finite element computer codes in perfor*i^g design and analysis of heavy industrial strucfures, systems, and components. At the Texas Utility Comanche Peak Nuclear Power Plant, Mr. Beigi administered and scheduled individuals to execute design reviews of cable tray supports; evaluated generic designcriteria for the design and construction of nuclear power plant systems and components and authored engineering evaluations documenting these reviews.A-11 ABSGonsultingAN ABS GROUP COMPANY FARZIN R. BEIGI. P.E. Mr. Beigi has also been involved in a number of seismic risk assessment and equipmentstrengthening programs for high tech industry, biotech industry, petrochemical plants and refineries, and industrial facilities. Selected project accomplishments include:Most recently performed Seismic Qualification of Critical Equipment for the Standby DieselPower Plants Serving Fort Greely, and Clear Air Force Station, Alaska. Projects also included design of seismic restraints for the equipment and design of seismic supports for conduit, cable tray, duct, and piping systems. Both facilities are designated by the Department of Defense as a Seismic User Group Four (SUG-IV) facitity. Seismic qualification of equipment and interconnections (conduit, duct and piping) involved a combination of stress computations, compilation of shake table data and the application of experience data from past earthquakes. Substantial cost savings were achieved by maximum application of the experience data procedures for seismic qualification.. Assessment of earthquake risk for Genentech, Inc., in South San Francisco, CA. The risk assessments included damage to building strucfures and their contents, damage to regionalutilities required for Genentech operation, and estimates of the period of business interruption following a major earthquake. Provided reconunendations for building or equipment upgrades or emergency procedures, with comparisons of the cost benefit of therisk reduction versus the cost of implementing the upgrade. Project included identificationof equipment and piping systems that were vulnerable under seismic loading and design of retrofit for those components, as well as, providing construction management for installation phase of the project.. Fault-tree model and analysis of critical utility systems serving Space Systems f Loral, a satellite production facility, i. Palo Alto, CA.. Seismic evaluation and design of retrofits for equipment, tools and process pipin B, as wellas, clean room ceilings and raised floors at UMC FABs in Taiwan.. For LDS Church headquartered in Utah, performed seismic vulnerability assessment and ranked over 1,,200 buildings of miscellaneous construction Wpes for the purpose of retrofit priorTttzation.. Seismic evaluation and design of retrofits for clean room ceilings at Intel facilities in Hillsborough, Oregon.. Assessment of programmable logic controls as part of year 2000 (Y2K) turn over evaluationat an automatic canning facility in Stanislaus, ca.. Seismic evaluation and design of retrofits for equipment and steel storage tanks at the Colgate-Palmolive plant in Cali, Colombia.. Design of seismic anchorage for equipment and fiberglass tanks at the AMP facilities in Shizouka,lapan.. Evaluation and design of seismic retrofits for heavy equipment, and piping systems at Raychem facilities in Redwood City and Menlo Park, CA.. Assessment of the seismic adequacy of equipment, structures and storage tanks at the Borden Chemical Plant in Fremont, CA.A.T2 ABSGonsultingAN ABS GROUP COMPANY FARZIN R. BEIGI. P.E. o Design of seismic bracing for fire protection and chilled water pipitg systems at theGoldman Sachs facilities in Tokyo, Japan.. Design of seismic retrofits for low rise concrete and steel buildings and design of equipment strengthening schemes at AVON Products Co. in ]apan.. Managed the design and construction of seismic retrofits for production equipment andstorage tanks at Coca Cola Co. in ]apan.. Seismic evaluation and design of retrofit for equipment piping and structures at the UDSAVON Refinery located in Richmond, CA.. Seismic assessment and peer review of the IBM Plaza Building, a31. story high rise buildi^glocated in the Philippines.. Seismic evaluation and conceptual retrofit design for the headquarters building of the San Francisco Fire Department. o Equipment strengthening and detailed retrofit design for the Bank of America Builditg i^San Francisco.. Equipment strengthening and detailed retrofit design for Sutro Tower in San Francisco.. Equipment strengthening and detailed retrofit design for Pacific Gas & Electric (PG&E)substations in the San Francisco area.. Seismic evaluations and loss estimates (damage and business interruption) for numerous facilities in lapan, including Baxter Pharmaceuticals, NCR ]apan Ltd., and Somar Corporation.Seismic evaluation of concrete and steel buildings at St. Joseph Hospital in Stockton, Ca, in accordance with the guidelines provided in FEM A178.EDUCATION 8.S., Civil Engineering, San Francisco State University, San Francisco, CA, 1982 REGISTRATION Professional Engineer: California Seismic Qualification Utilities Group Certified Seismic Capability Engineer Training on Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns AFFILIATIONS American Society of Civil Engineers, Professional Member SELECTED PUBTICATIONSM. Richner, Sener Tinic, M. Ravindra, R. Campbell, F. Beigi, and A. Asfura, "Insights Gained from the Beznau Seismic PSA Including Level 2 Considerations," American Nuclear SocietyPSA 2008, Knoxville, Tennessee. A-13 ABSGonsultingAN ABS GROUP COMPANYFARZIN R. BEIGI,U. Klapp, F.R. Beigi, W. Tong, A. Strohm, and W. Schwarz, ,,Seismic PSA of Neckarwestheim 1 Nuclear Power Plant," 19th International Conference on Structural Mechanics in Reactor Technology (SMIRT 19), Toranto, Canada, August 12-17,2007.A. P. Asfura, F.R. Beigi and B. N. Sumodobila. 2003. "Dynamic Analysis of Large Steel Tanks." 17th International Conference on Structural Mechanics in Reactor Technology (SMIRT ln,Prague, Czech Republic, August 17-22,2003."seismic Evaluation Guidelines for HVAC Duct and Damper Systems," April 2003. EPRITechnical Report n07896. Published by the Electric Power Research Institute. Arros, I, and Beigi, F., "seismic Design of HVAC Ducts based on Experienced Data." CurrentIssues Related to Nuclear Plant Structures, Equipment and Piping, proc. Of the 6th Symposium,Florida, Decemb er 1996. Publ. by North Carolina State University, 1996.F.R. Beigi and I. O. Dizon. 1995. "Application of Seismic Experience Based Criteria for SafetyRelated HVAC Duct System Evaluation." Fifth DOE Natural Phenomenon Hazards Mitigation Symposium. Denver, Colorado, Novemb er 13-1,4, 1995.F.R. Beigi and Don R. Denton. 1995. "Evaluation of Bridge Cranes Using EarthquakeExperience Data." Presented at Fifth DOE Natural Phenomenon Hazards Mitigation Symposium. Denver, Colorado, November 13-'1,4, 1,995.A-14 ABSGonsultingAN ABS GROUP COMPANYEDDIE M. GUERRA, E.I.T.PROFESSIONAL HISTORYABSG Consulting Inc,, Contractor, PresentlyPqul C. Rizzo Associates,Inc,, Pittsburgh, PA, Assistant Project Engineering Associate, PresentlyThornton Tomasetti, Inc., Philadelphia, PA, Structural Engineer Interry]anuary 2009-june 2009Skanska USA,, Inc., San Juan, Puerto Rico, Civil Engineering Intern, May 2008-July 2008 Nettuork for Earthquake Engineering Simulation, Bethlehem, PA, Research Assistant Muy 2007-Iuly 2007 PROFESSIONAL

SUMMARY

Mr. Eddie M. Guerra, E.I.T. is an Assistant Project Engineering Associate with Paul C. RizzoAssociates, Inc. (RIZZO). Mr. Guerra has been involved primarily in the structural design and analysis of power generation strucfures in both nuclear and wind energy sectors. Mr. Guerra specializes in strucfural dynamics, Performance Based Seismic Design methodologies andelastic and inelastic behavior of concrete and steel strucfures. He is fluent in both English and Spanish.PROFESSIONAL EXPERIENCE Nuclear:AP1000 HVAC Duct System Seismic Qualification -October 2010 - PresentSSM/ Westinghouse Electric Compan/, Pittsburgh, Pennsylvania:Engineer for the seismic qualification of AP1000 HVAC Duct System.Structural dynamic analysis of all mayor steel platforms inside steel containment vessel.Investigation on the interaction of steel vessel and HVAC system displacements due to normaloperational and severe thermal effects.Finite element modeling of HVAC access doors under static equivalent seismic loads.Followed AISC, ASCE and SMACNA standards for the qualification of steel duct supports.A-15 ABSGonsultingAN ABS GROUP COMPANYEDDIE M. GUERRA. E.I.T.Wind:Analysis and Design Reaision of Wind Turbine Touter -October 2010 - February 2011 Siemens, Santa Isabel, Puerto Rico:Engineer for the analysis and design revision of a wind turbine tower to be constructed in SantaIsabel, Puerto Rico.Developed design criteria based on local building code requirements and the International Electrotechnical Commission (IEC) provisions for wind turbine design.Dynamic analysis of wind turbine.Design revision of turbine tower shell, bolted flange connections and global stability of the tower.EDUCATIONM. Eng., Structural Engineering, Lehigh University, Bethlehem, PA - Muy 2010 8.S., Civil Engineering, University of Puerto Rico, Mayaguez, PR - Dec. 2008 SKILL AREASStructural AnalysisSeismic Design Reinforced Concrete DesignStructural Steel Design Wind Aerodynamics Wind Turbine DesignPlastic Steel Design Foundation Design COMPUTER SKILLSSTAAD, ANSYS, AutoCAD, ADAPT, SAP2000, RAM, MATHCAD, PCA Column, MS Office REGISTRATIONS Engineer-In-Training: Puerto Rico - 2009 MEMBERSHIPS American Society of Civil Engineers (ASCE) American Concrete Institute (ACI)Network for Earthquake and Engineering Simulation (NEES)U.S. Dept. of Labor (OSHA)Society of Hispanic Professional Engineers (SHPE) A-r6 ABSConsultingAN ABS GROUP COMPANY EDDIE M. GUERRA. E.I.T.HONORS AND AWARDS201,0 Recipient of the Thornton Tomasetti Foundation ScholarshipGolden Key International Honor SocietyTau Beta Pi Engineering Honor SocietyUniversity of Puerto Rico at Mayaguez Dean s List PUBLICATIONSGuerra, Eddie M., "Impact Analysis of a Self-Centered Steel Concentrically Braced Frame,"NEES Consortium, May - I.rly 2007.A-T7 ABSGonsultingAN ABS GROUP COMPANYADAM HELFFRICH, E.I.T.PROFESSIONAL HISTORYABSG Consulting Inc., Contractor, PresentlyPnul C. Rizzo Associntes, Inc., Pittsburgh, PA, Assistant Project Engineer,2009-PresentPenn DOT, Clearfield, PA, Interry Muy 2008-August 2008TNS, Indiana, PA, Surveyor/ April 2007-Aupst 2007Shaler Area School District, Glenshaw, PA, Maintenance, Muy 2005-August 2406 PROFESSIONAL

SUMMARY

Mr. Adam Helffrich joins Paul C. Rizzo Associates, Inc. (RIZZO) as a Project EngineeringAssociate. He recently received his Bachelor of Science in Civil Engineering from the University of Pittsburgh. Prior to graduating, Mr. Helffrich was an Engineering Intem with RIZZO.PROFESSIONAL EXPERIENCEIIAE Site A (Alternate) NPP Site Selection/Site Characterizatiory'PsAR and EIAENEC/KEPCO EtC, United Arab Emirates: May 2009- August 2009 RIZZO prepared the site investigation and submittal of a PSAR and ER to the RegulatoryAuthority Ior the siting of Nuclear Power Plants (technology to be decided). Mr. Helffrichdeveloped and reviewed boring logs for both sites; constructed drawitgt of cross sections for a site; and performed several checks and modifications to figures and slides for presentation purposes.Cqktert Cliffs NPP Unit 3 - UniStar, Calztert County, Maryland: Moy 2009 - August 2009Mr. Helffrich was responsible for cutting several cross sections of the sub surface for analysis Purposes.A-18 ABSGonsulting AN ABS GROUP COMPANY ADAM HELFFRICH, E.I.T.PREVIOUS EXPERIENCE P enn DOT - Clearfield, P ennsyla ania:Moy 2008 - August 2008 Intern:Conducted STAMPP program for roadway safety;Worked independently and unsupervised through several counties;Studied technical diagrams of roadways and foundations; and Applied gathered knowledge in roadway safety reports.fNS - Indiana, Pennsyhtania: April2007 - August 2007 Surveyor:Conducted Research surveys and polls for various clientsShaler Area School District - Glenshana, Pennsylaania:Moy 2005 - August 2006 Maintenance:Light Construction/ Building Maintenance Janitorial EDUCATION 3-2 Pre-Engineer Program, Indiana University of Pennsylvania, Indiana, PA, Graduated 2008 COMPUTER SKILLS C**, Mathematica, AutoCAD A-19 Resume ofMohammed F. Alvi, P.E.

SUMMARY

. Thirty-three years of experience as an engineering professional (27 years in nuclear). Professional Engineer, registered in the State of New York, USA Completed the Boiling Water Reactor (BWR) Plant Certification Course for Nine Mile Point Unit-lNuclear Station Experience as a Structural Design Engineer, Engineering Supervisor for StructuralAvlechanical Design and Plant Support Engineering, Manager MechanicaVStructural Design and Project Manager. Innovative and resourceful engineer with problem solving skills. Excellent leadership skills with proven record. Excellent analytical, design, decision making, communication, organizational, and interpersonal skills. Proficient in computer skills EXPERIENCE:

June 2012 -Present March 2008 -May 2012 First Energy Nuclear Operating Company Senior Consulting Engineer Project Manager for Seismic Probabilistic Risk Assessment (SPRA) Project. Responsibilities include vendor oversight for 50.54(0 Letter Seismic 2.1 and2.3 as well as technical overview of the SPRA project.Bntergy Nuclear Operations James A. Fitzpatrick Nuclear Power PlantOswego, New YorkSupervisor, MechanicaUCivil Design Engineering Responsible for supervising a group of 10 mechanical/civil/structuralengineers at the James A. Fitzpatrick Nuclear Plant. Responsibilitiesincluded issuing plant modifications, evaluations, engineering changes,equivalency changes, supporting refueling and forced outages, acted as engineering duty manager, identified training needs, participated in thedaily fleet telephone calls, resolved operability issues related to degradedconditions, assisted in resolving plant emergent issues, responded to USNuclear Regulatory Commission (NRC) Resident questions, supportedemergency response organization duties, etc. Oversight of constructionactivities, owner acceptance of AIE Consulting Firm design. Performedduties of acting design engineering manager, trained staff ontechnical/administrative skills, etc.Public Service Electricity & Gas (PSEG) NuclearFebruary 2OO7 -A-20 February 2008 1988 - Oct. 2006 Hope Creek Nuclear Generating Station Branch Manager, MechanicaUStructural Design Responsible for managing a staff of 8 Mechanical/Structural engineers atHope Creek Nuclear Generating Station. Responsibilities included analysis, design of Structures, Systems, Components, resolving operability issues, preparing design change packages, evaluating non-conforming conditions, addressing short and long term issues for the station, supporting outages, address training needs of the group, participate inPlant Health Committee, interface with resident NRC inspectors, etc.I was also responsible for performing the duties as the site reviewer of all Structural/IVlechanical related license renewal documents being preparedby the License Renewal Group. I was implementing the Hope Creek primary containment (Drywell and Torus) ageing management program to support the license renewal process. I was also assisting in the implementation of FatiguePro software at Hope Creek.Nine Mile Point Nuclear Station (Constellation Nuclear)Oswego, New YorkEngineering Supervisor/Principal Engineer Responsible for analysis, design and maintenance of various nuclear power plant structures at Nine Mile Point Nuclear Station Units l & 2. Analysis includesdesign of reactor building superstructure, turbine building superstructure, yard structures, masonry wall design, piping analysis and supports for safety related systems, cable tray supports and various electrical and mechanical components supports, etc.Supervised a group of 10 engineers/designers, coordinated projects with site engineering consultants, performed engineering evaluations and cost benefit studies for various projects for an economical design.As one of the leaders of the engineering organtzation,I directed and supervised individuals technically and administratively to make sure the job is done correctly the first time and per schedule. I had the decision making authority for all structural engineering issues at the station.License Renewal: I was also the Manager for Fatigue Monitoring Program forNine Mile Point Nuclear Station, Units 1 & 2. I was involved in setting up the software "FatiguePro" at the station for a cost of $500K. This was in commitment to the Nuclear Regulatory Commission as part of License Renewal program for NMP station. This program included identifying the various transients that the plants were originally designed for, historical count of transients, identifying cumulative usage factors at critical locations, identifyingwhat locations CUFs will be exceeded for a 60 year plant life and what actions were needed to resolve the same. Also addressed the environmental fatigue issues.A-21 1983 - 1988I was also responsible for managing all structural aspects of license renewalprogram at the station. This included preparation of program basis documents (e.g., masonry walls, bolting, monitoring of structures, etc.), scoping documents, ageing management program documents, time limiting ageing analysis (TLAAs),performed walkdowns for defining boundaries.I was also part of the design team that gave a presentation to NRC license renewal team at Rockville, MD regarding the primary containment ageing management program for torus and drywell shell thickness at Nine Mile Point Unit-l.Note: I was also the Nine Mile Point Nuclear Station Lead for the NRC Component Design Bases Inspection (CDBI) that was conducted in September/October 2006. I successfully lead the NMP team, supported the inspection with no major violations for the station. This project started in May2006 which included self assessment (mock inspection), taking appropriate corrective actions prior to the actual inspection for a successful outcome.Acting Manager, Engineering Unit 1 Nine Mile Point Nuclear Station Performed the duties of an engineering manager, attended the daily leadership meetings, resolved the plant issues, prioritized and coordinated the work activities of various disciplines in Engineering, conducted branch staff and safety meetings, successfully resolved all engineeringissues during this period for safe operation of the plant.Supervisor, CiviUstructural Engineering, Unit L Nine Mile Point Nuclear Station Responsible for all structural engineering issues at Nine Mile Point Unit.Major accomplishments as Structural Supervisor included implementation of Structural Maintenance Rule Program, development of various engineering specifications and drawings for the older vintage plant.Attended various structural seminars on Seismic Qualification Utility Group (SQUG), concrete and masonry walls, structural maintenance program, completed various training on leadership skills, supervisory skills, performance appraisals, effective communication, Labor training, Leadership Academy and completed two weeks of training at Institute of Nuclear Power Operations (INPO)-Atlanta for Engineering Supervisors Professional Development Seminar.Sargent & Lundy Engineers Chicago, Illinois Lead Structural Engineer Responsible for analysis and design of various nuclear power plant structures using ACI and AISC codes, was responsible for designing pipe supports, conduit supports, pipe whip restraints, masonry walls, steel frames, used various in-house computer programs for analysis A-22 1978 - 1983 desi gn, performed walk-downs, performed structural calculations,resolved non-conformance reports, performed seismic qualificationcalculations, etc. Klein & Hoffman, Inc Consulting Engineers, Chicago, Illinois Structural EngineerStructural engineer responsible for analysis and design of schools,parking garages, industrial buildings, high rise buildings, sewage treatment plant structures, etc. Extensively used AISC and ACI codes and various in house computer programs for analysis and design.EDUCATION:. Master of Science (Structural Engineering), University of Illinois, Chicago (1977)o Bachelor of Engineering (Civil), Bhopal University, India (1976)PROFBSSIONAL LICENSES/CERTIFICATIONS :. Registered Professional Engineer, State of New York. Boiling Water Reactor (BWR) Plant Certification Course for Nine Mile Point Unit-l Nuclear Station PROFESSIONAL SOCIBTY MEMBERSHIP: o Member, American Society of Civil Engineers (ASCE)

REFERENCES:

Provided upon request CITIZENSHIP:Citrzen of the United States of America A-23 Richard P. Mueller Sreet Addrers 111{i I:ine Street, East Lirerpool, Oh, 439!SPhone Nrrrnbpr 530-385d-5{i3,nEmgil addresc nruet2ofid.roncf, st'De tTFork Eqp*ri*rlcc Dugr.resn* I.ight Core;raav and Firct Energv Couporation Iqh-Tirhr Hons* errd 1'=d L*borer Coe! ud as,b hufler5rr*lerr Operaro'r Eer:rerltellqr L:nit I Lie*ssed Reas:nr Qpermr Beawc Vil*T Urit I liessed Secicr Rcec*or Opmtor Eeever \tdlef Uan I eod Urdt 3 Educatisfl 9,,r8/1975 to 7/5113*l I Degreer Fenn Stare Utnir-'ercitt' Asrod.ue D*gr* irl Nudeer Eaglnaerng Techrologhlurleatr Forr.er Plant Related Skills and Bxpcriences Operniocs l*rd foc th* l*t &ree NRC Tri*noirt Fire Protecrio{l ic5pestiotts-D* dop*d tbe Ogerxions tb*lisrs eod stretq$es for &e Letc+t Appendlx R a.ad Sefo Shrrtdnwr froctdrtcer for Eeerer l'rllqUait 1 rlrd Uait 3 I0CFR5{}.5S a*d kdegreadem qur}i6ed Rcryicsrer ,IQRi qnaliEed Oprsiorrr l*ad for refinding outage rchedulrog aodplroarog-D*EdoFed rlemrte strateg*as rnd effitieccr iaproFern*lrte for Opecatiaa: groced:res a.od t*sts-Ass$ted is &E derelopmmt *f &e letest l0 yeer ASttF tes'ioS Fograrn far Bearer l':Eery Usit I ud Uoit 3 .A-24 g o E9.-f;p$qsE EEq#'$:r 6 j\t(f*l+f't r-.c\l q)E=o (J L ou Etr-y fn 3 ftr*F g-=E.9E EE3 FE r'l l-trtr FOE Otrul z ='iil-Lf/l=o etrH bfiO b Hg-Ig'E a'rrl Itr L F d-c{rJ a0 d-rts 15'15{)f4---I rT c FI FT\$.t- I Lt a)F$s h hr rQ\-/\-*Q-q)\r\r s q.J frr h.trrt t.tI UJ=ct EF 72 Q=&*uu Fi gH=rr1 sc: tlI tt tI t at-.tlr 3U {ji T.\EH o*' EF ff H T ffi t./q)s*i+ \*FJ F.,b -s\sn \J=F^Y.ts S.Ht'--'s-o\.O au fr\-Y r *- '=i-t Yh-i\Iqr \'-\Srf (b.B "'.i a+IJ 5/,S R%'E L\ b.qr;F S'E t-..H S ir h').S H*b ,i 'il.6 N t4.\S\E,tI FI H EEh FT.9r 'ts\./ H tt\ qI.!i *\qL}rn tr o{J EN tr II E E o tr4 I UJ*r qj Ls*Ir*t+tr fl O+t ,3 trl't-i\s t{*T tl Fr ql FI t-r Tr$-$LS u-x.gt ql l$EI TA-Y LI lrll'!H$;).D;c'. vl il}td i,H iFr lE td I;{.:F.I Er I aE rE?I raEi r{t}l :r I HF; +st rE# aP-_- -_?.\4-" 14-L-1 -\ur-tr O" trrh.S{96 FEt^ rB il 11 t}IH gs EO F: g#A b$.oI)ag&0?n ll+, d'gH fis{"=EE tro EE g's u.E fr.9 6.!l 4F EH Tg nEn dt E t,r.F d s C)GI!]CT w tr o FT rFl*F4 I fi*f}H E FT+&d rd$It trtTt3 .5 Frl tr trtn a flp En itrI t-' a - --t-) F?-FFt a+a -l t* c+a'= $+a G+tr q*9tr d te EI FJ*rlJ tn I fra O+H e ffi ts a+flJ NI l*ET H qra trT F-*{+{Fft tH af-+f t{tr H tr tH TR rts'tR rF F./tt H r{nf F ts+g+++#4&+g+d'q*g+r {H#{r._r q t*L-Et l. -*,!,'a tF+E S+r+ffim+f,*{+{{r tF-$r{d rFf t*g+H H II, tril 1t Li lft tl t)il 1!1o ii.F sgF EEfr EE$l j\E*hl (}CrI{{ft CI 3 fic o C'l-oln Etr rfn 3 ttt I Ery*F tr-=E.gE EH3 FE rr Lg';trqf;Otrln z E'iil EEl/1 crg?!broOL HErg'E Ei-rrl TE b F rts as rl q)E d H rl N tr G F=trrl\e r lhl\hrl q)Frl s R E L\rL- t- --t1 lII LI.--\.*Q'AJ\+\l s tJ frr.b-t\r tr Fai LII--t\LI ta?sE E?B=*t EH ID rlt lJ*IT r trf o\c{I F.\\Tr s q FI fh LH (5l TU+r FT Tr\)tit R$$)*I qt-.r[\t-1 -T-r LI-. -a lE.-7 ea I[t (J}r o s t\lr$0 ril+r[t t n fi o u tH o fit*r fif g TE rfl+r t{{l L}FI3I Ft'tr s q rh\ll\\s (5,', C\t TH ci st\rf T H q q)H\l^tr*\H$F'I-l T...-\-- r t tI.'q IFE- I II-tt!.S r{rf rt$rFl\*s HT q\TT tr rt s tr rpl FI h q)H q FT*--.tI rA\-I L-F 1---r.-rll s S (5\\)s\s)+r*$I I s (5\\)s\s)+r*$I\q F rT AJ rtrr{+r FT tr-\)II H s)t.r tllLt I-JT tl Lr-.-- N co I fit;-{o N (o.ut 5 trf J o gl t{o rfl 6 h t{ttr)\rl h s rts\s q H g ril+r[t H Fh E g u t{.f 0 u*f fif tl H rH+r k{l L} ca ca I gH Gi 4 ,g ffi*3#f: F,; '{j ET FF'Fl tr1 TI\s:\!Ils r fr'Fl I*.1 f*f, n(}r'l*Fr T.q)"*frr Tr ql t5 ,$rq TJ ql-l .b tA Tr-ql\J (rt*FI rs*t q'Hf hl!r H t, rI.lh_-- s'tr.,g EeE fEE E*$rg a j\t(f'I#.(\l F-*c.l a g o (J l-o {r}Lt, =.vtY! 3 Er*F C-=c O-ETETE EE3 F]tr u aD LLr-qqE otruf-, r- rr z=of EEl/1 go{j sPh- - -r- tr-g rrt tE L l-.-E r?5{J fr H-d FI-G A t c E$r l\Q tr l t'l q)I\hl s tr T-r s U\*s'q)\\I t q.J f t\r.ht LI t\J U F 3 rttr 3g o*GLry si LJU q**llr l-P t-fr II It w III rll!t I E f," Frh ttE 0dt hf, Is ,rd sr P;H*J nr b$!:)o0 E,w T8 ot*6 ar o gt n 4&EX ts.5 tf f+ ,:.gT i6 nA Tru ,EG f. lr+rfr 4e ft(l$\,){\$.s FI o u t trt J**d It F tr s E E c fJA rI f,g'E .*llc vt .fi.(J O" 15 dd a(h l.t o*c 0)E n$t{S J.$os u :t sh,r, 6* Q}y s+ o})-{ !i 4'E tF -t'E :I cu# ET A p Et :? t'.R. P i g,s E$s il 0J *S +r-C \F fu ,r-J $ n- q)'i N' Tn*.Eg O S* E*EedT iEE =dE LrO ,e$(Ja (n 6-'4 rr-1 rF{r-{I Fi TJ q)A H H A H H c-1+{e E+J d t-t r-{{J h+{{J h 0)U o*J r?U].F{d.-{F f,J+J d TJ rF{q{-,{r r={+J t-+U U \o ca I fr.ca I}}