ML082530272
| ML082530272 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 07/23/2008 |
| From: | Horowitz J - No Known Affiliation |
| To: | NRC/SECY/RAS |
| SECY RAS | |
| References | |
| 06-849-03-LR, 50-271-LR, Entergy-Applicant-E4-02-VY, RAS M-317 | |
| Download: ML082530272 (5) | |
Text
/-Ac-S H-S 112 DOCKETED USNRC August 12, 2008 (11:00am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF RESUME Jeffrey S. Horowitz, ScD PROFESSIONAL EXPERIENCE 1985 - Present Independent consultant working in the nuclear and mechanical engineering fields. Consultant to EPRI (Electric Power Research Institute) on single and two-phase flow-accelerated corrosion (also known as erosion-corrosion), cavitation, thermal-hydraulic analyses, void fraction correlation and service water corrosion.
Principal creator of CHEC, CHECMATE and CHECWORKS, the computer programs which predict single-phase and two-phase flow-accelerated corrosion. CHECWORKS is currently used to improve maintenance efficiency and enhance safety in more than 150 nuclear units worldwide.
Consultant to Arizona Public Service, the CANDU (Canadian Deuterium Uranium reactors) Owners Group, Exelon Corporation, Ontario Power Generation, Inc., Pacific Gas & Electric and Southern California Edison on issues of flow-accelerated corrosion and nuclear safety.
Co-author of three books and 34 published EPRI reports. Sole author of 16 published EPRI reports.
1980-1984 Program Manager, U.S. Department of Energy, 9800 South Cass Avenue, Argonne, Illinois, 60439, 630-252-2000, Frank Herbaty, supervisor:
Managed substantial portions of the Industrial Co-generation, Magneto-hydrodynamics (MHD) and Ocean Thermal Energy Conversion (OTEC)
Programs at the Chicago Operations Office. The annual value of the work I managed was about $10 million.
Promoted from GS- 13 to GS- 14.
1977 - 1980 Mechanical Engineer, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, 630-252-2000. D..Norman Sather, supervisor: IUULr.,-tl i~t3uLATfV IntheMatterof 5lLý¶> tjje Oocket No, .,L...-.p jV.~j~j, Official Exhibit No.--"i --, U'f OIFFERED t)FFERED by4 ý)by Intervenor NRC Staff Other W2Iwinessmpanol-K FJC g IDENTIFIED) oni3&3 Adton TakmW REJECTED W NIWN
Government Technical Manager on several, multi-million dollar OTEC power systems studies and heat exchanger construction programs.
Conducted design studies, computer modeling and laboratory testing on a metal-hydride heat pump system.
Promoted from Assistant Mechanical Engineer to Mechanical Engineer.
1973-1977 Principal Engineer, Combustion Engineering, 1000 Prospect Hill Road, Windsor, CT 06095, 860-688-1911, Dr. Hector Guerrero, supervisor:
Lead engineer on a series of nuclear safety experiments including tests on an alternate emergency core cooling system, steam generator depressurization, re-flood heat transfer and an innovative primary system flow meter.
1972-1973 Nuclear Engineer, Quadrex Corporation, 477 Division Street, Campbell, California, (company now defunct), Randolph Broman, supervisor:
Conducted various nuclear safety analyses.
Wrote and modified computer programs (e.g., RELAP and CONTEMPT) related to nuclear safety. The areas of focus included boiling water reactor loss of coolant accident analysis, pipe rupture loads and effects, building pressurization and hydraulic loads resulting from valve closure.
REFERENCES Professional and personal references available on request.
EDUCATION ScD Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, 1972 Mech Eng Mechanical Engineering, Massachusetts Institute of Technology, 1968 MS Mechanical Engineering, Massachusetts Institute of Technology, 1968 BSME Mechanical Engineering, Magna Cum Laude, New Jersey Institute of Technology, Newark, NJ 07102, 1966 Bayonne High School, Bayonne, New Jersey 07002 HONORS American Nuclear Society, Fellow American Society of Mechanical Engineers, Fellow Sigma Xi (Honorary Scientific Research Society)
National Science Foundation Graduate Fellowship Tau Beta Pi (Engineering Honor Society) 2
(.
Pi Thu Sigma (National Mechanical Engineering Honor Society)
Honors on Admission, New Jersey Institute of Technology PATENTS AND PUBLICATIONS U.S. Patent - Patent Number 4,372,376, Heat Pump Apparatus, February 8, 1983.
Books Co-author of the EPRI book, PressureDrop Technology for Design andAnalysis, published 1999.
Co-author of the EPRI book, Flow-Accelerated Corrosionin Power Plants, published 1996 and revised in 1998.
Co-author of the EPRI book, Void FractionTechnology for Design and Analysis, published 1997.
PublishedRepokts - sole author of the following EPRI Reports Development of an Averaged Point-to-PointMethodfor Inspection Data, EPRI, Palo Alto, CA, to be published.
Investigation into CombiningSingle and Multiple Outage Inspection Data, EPRI, Palo Alto, CA, to be published.
Development of a Figureof Meritfor EvaluatingCHECWORKSrM SFA Pass 2 Results, EPRI, Palo Alto, CA, to be published.
Investigation into Flow-Accelerated Corrosionat Low Temperatures,EPRI Report, 1013474, November 2007.
Flow-AcceleratedCorrosion- The EntranceEffect, EPRI Report, 1015072, November 2007.
Interim Recommendationsfor an Effective Program againstErosive Attack, EPRI Report, 101507, December 2007.
Investigationinto Flow-AcceleratedCorrosion at Low Temperatures, EPRI Report, 1013474, November 2006.
Computer-BasedTrainingModule on Erosion in PipingSystems, EPRI Report 1013570, November 2006.
Computer Based TrainingModule on Flow-Accelerated Corrosion(FA C)for non-FAC Personnel,EPRI Report 1013249, May 2006.
DeterminingPiping Wear Causedby Flow-AcceleratedCorrosionfrom Single-Outage Inspection Data, EPRI Report 1013012, March 2006.
3
An Evaluation of Flow-AcceleratedCorrosionin the Bottom HeadDrainLines of Boiling Water Reactors,EPRI Report 1013013, March 2006.
Chemistry Effects on Flow-AcceleratedCorrosion- PWR: Hydrazine and Oxygen Investigations,EPRI Report 1011835, November 2005.
Chemistry Effects on Flow-AcceleratedCorrosion- B WR: Dissolved Oxygen Investigation,EPRI Report 1011833, November 2005.
Recommendations for Controlling Cavitation, Flashing,LiquidDroplet Impingement, and Solid ParticleErosion in Nuclear Power PlantPiping Systems, EPRI Report 1011231, November 2004.
Flow-AcceleratedCorrosionInvestigations of Trace Chromium, EPRI Report 1008047, November 2003.
Selective Attack of Welds by Flow-Accelerated Corrosion,EPRI Report 1007057, July 2002.
Published Reports - co-author of the following EPRI Reports Recommendationsfor an Effective Flow-Accelerated'CorrosionProgram(NSA C-202L-R3), Non-ProprietaryVersion, EPRI, Palo Alto, CA: 2007. 1015425.
Recommendationsfor an Effective Flow-Accelerated CorrosionProgram(NSA C-202L-R3), EPRI Report 1011838, May 2006.
Recommendationsfor an Effective Flow-Accelerated CorrosionProgram,NSAC-202L, Revision 2, April 1999.
CHECUPTM , a CHECWORKSrM Application for FAC Evaluation of Fossil Power Plants- Users Guide, EPRI TR-103198-P5, November 1998.
CHECWORKSrM Computer Program Users Guide, EPRI TR- 103198-P 1, December 1997.
Guidelinesfor ControllingFlow-Accelerated Corrosionin Fossil Plants, EPRI TR-108859, November 1997.
Recommendationsfor an Effective Flow-AcceleratedCorrosion Program,NSAC-202L, Revision 1, January 1997.
Understanding Void Fractionin Steady State and Dynamic Environments, EPRI TR-106326, August 1996.
Recommendationsfor an Effective Flow-AcceleratedCorrosionProgram,NSAC-202L, November 1993.
An Analysis of BWR Fuel Heatup During a Loss of Coolant While Refueling, NSAC-169, November 1991.
CHEC-NDErm a Tool for Managing Non-Destructive EvaluationDatafrom Pipe Inspections, EPRI NP-7017-CCML, NSAC- 149L, April 1991.
CHECMA TETM Computer Program Users Guide, NSAC-145L, Original May 1989, and Rev. 1, April 1991.
4
The Chexal-Lelouche Void FractionCorrelationfor GeneralizedApplications, NSAC-139, April 1991.
CHECComputerProgram Users Manual,NSAC- 112L, Original July 1987 and Rev. 1, July 1989.
An Assessment of Eight Void FractionModels for Vertical Flows, NSAC-107, December 1986.
A Full-RangeDrift-Flux Correlationfor Vertical Flows (Revision 1), EPRI NP-3989-SR, September 1986.
Response of a B& W Plant to Steam GeneratorTube Ruptures, NSAC-101, September 1986.
EPRIR&D Contributionsto the TechnicalBasis for Revision of ECCS Rules, EPRI NP-4146-SR, July 1985.
Technical Papers - More than 45 published technical papers on nuclear safety analysis, thermal-hydraulics, and flow-accelerated corrosion.
5