ML12335A404

Official Exhibit - RIV000004-00-BD01 - Curriculum Vitae of Joram Hopenfeld (Hopenfeld Cv)

ML12335A404
Person / Time
Site:	Indian Point
Issue date:	12/22/2011
From:	Hopenfeld J Riverkeeper
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21600, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12335A404 (6)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:

Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:

Identified:

Admitted:

Withdrawn:

Rejected:

Stricken:

Other:

RIV000004-00-BD01 10/15/2012 10/15/2012 RIV000004 Submitted: December 22, 2011 c,.",tJ"oP< REGlJ<..q"

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• • • • il Curriculum Vitae for Dr. Joram (Joe) Hopenfeld 1724 Yale Pl., RocIcville, MD 20850 Tel: 301 340 1625

. A. Professional Expertise:

a. Nuclear Safety aDd Licensing (design basis/severe accidents)

b. ThermallHydraulics (Transient Boiling, Jet Mixing, Reentry Heat transfer, molten metal/coolant interactions, pool fires, computer code developments)

c. MaterialslEnvironmeot Interaction (corrosion, erosion, stress corrosion, fatigue,.

cavitation, fouling)

d. Radioactivity Transport (10 eFR Part 100 )

e. Industrial Instrumentation and EDvironmentaJ Monitoring.

B. Current Position - CEO, Noverflo, Inc C. Education - Engineering-University of California at Los Augeles: BS 1960, MS 1962, Ph.D 1967.

D. Summary of Work Experience

1. Nuclear Plant Related Experience I have 4S years of experience in industry and government primarily in the areas of thermal hydraulics,

. materials, corrosion, radioactivity transport, instrumentation, PWR steam generator transient testing and acoidentanalysis. I have managed major international programs on steam generator perfonnance during steam generator tube ruptures, steam line and feed line breaks. Following a decade of studies and severa) Advisory Committee on Reactor Safety hearings, the Nuclear Regulatory Commission, ("NRC")

adopted my position regarding the safety consequences of operating with degraded steam generator

tubes.

In 2001 the NRC initiated a major program on the effects of steam generator tube degradation on plant safety (see NRC website). I have consulted to law firmsand citizen groups regarding Steam Generators, Thermal Hydraulics, Corrosion, and Material Fatigue in connection with license renewals and a power upgrades.

2. NOD Nuclear Related Experience I am the owner and the CEO of a small Maryland company. Noverflo. Noverflo is developing advanced fiber optic sensors for the oil & gas and the envirorunental monitoring industries. In 2004 Noverflo has completed a three year progr8m which was sponsored by the U.S. Department of Energy. The program produced a new system for automatic tank gauging, which will be presented at the 2006 National Petrochemicals and Refiners Association Maintenance Conference.

In 1994~ 1996 NoverfIo has developed and commercialized a shutoff valve for fuel tanks to comply with new EPA regulations.

E. Brief Elbploymeot History A. Recent Consulting

1. Winston & Strawn, 1400 L St. Washington D.C 2001 Provided assistance in connection with the February 2000 steam generator event at Indian Point.

2. C-IO Research and Education Foundation, Inc. 44Merrimac St. Newburyport, MA 2002-2003 Provided assistance in the preparation of a 2.206 petition to the NRC and other matters in connection with steam generator problems at the Seabrook Station

3. California Earth Corps (Sabrina D. Venskus, Attomeyat Law, Santa Monica, CA) 2005

Provided testimony to the Public Utility Commission of the State of California on behalf of California Earth Corps in connection with the San Onofre steam generator replacement project.

4. New ERgla.d Coalition (Raymond"Shadis. Edgecomb, Maine 04556) 20os..2006 Technical consultant and expert witness in connection with Vennont Yankee power uprate and life extension hearings before the Atomics Safety and Lkensing Board. Prepare contentions and testify before the Board.

B. Industry and Government Employment 1962-1971 -Corrosion testing of materials for the design and operation of liquid metal cooled nuclear reactors. Modeling Transient Boiling in water and sodium. Modeling Sodium Fires. Modeling destruction of SNAP fuel rods on reentry into the earth atmosphere. Atomics International, Canoga Park, Calif.

1971-1973-Participated in the resolution of design issues as related to material behavior in the Breeder reactor environment Atomic Energy Commission 1973 - 1978 Project Manager for the safety evaluation and testing of steam generators for liquid metal reactors. Managed the development ofthennal-hydraulic computer codes such as COBRA.

ERDAlDepartment of Energy. Responsible for testing material compatibility and cavitation damage in sodium. Developmentof acoustic leak detection systems for sodium/water reactions..

1918.- 1982 Project Manager for the development of materials and instrumentation for high temperature steam generators for fossil plants. Responsible for the resolution of issues relating to corrosion/erosion and NOx ISOx emissions, Department of Energy.

1982 - 2001 Program manager for the resolution of various, thermal hydraulics, material corrosion and safety issues primarily in relation to PWR steam generators. Nuclear Regulatory Commission.

Publieations

In addition to nwnerousreports, I have published 15 papers in peer-reviewed tecbnic8I journals in the areas ofthennal-hydraulics. corrosion! erosion, steam generator dose releases during accidents, steam explosions, sensors and ECM machining.

Peer Reviewed

New Fiber Optic Based Technology for Automatic Tank Gauging'\\ Sensors,December 2006

2.

"Distributed Fiber Optic Sensors for Leak Detection In Landfills", Proceeding ofSPIE Vol 3541 (1998)

3.

"Continuous Automatic Detection of Pipe Wall Thinning", ASME Proceedings of the 9th, International Conference on Offshore Mechanics and Arctic Engineering. Feb. 1990 4

"Iodine Speciation and Partitioning in PWR Steam Generators", Nuclear Technology, March 1990

5. "

Comments on "Assessment of Steam Explosion Induced Containment Failures" Letter to. the Editor, Nuclear Science and Engineering, Vol. 103, Sept. 1989

6.

"Experience and Modeling of Radioactivity Transport Following Steam Generator Tube Rupture", Nuclear Safety, 26,286, 1985

7.

"Simplified Correlations for the Predictions of No x Emissions from Power Plants". AIAA Journal of Energy, Nov.-Dec., 1979

8.

"Grain BOW1dary Grooving of Type 304 Stainless Steel in Anneo Iron Due to Liquid Sodium Corrosion". Corrosion, 27, No. t 1, 428, J 971

9.

"Corrosion of Type 316 Stainless Steel with Surface Heat Flux in 1200 Flowing Sodium",

Nuclear Engineering and Design, 12; 167-169, 1970

10.

"Prediction of the One Dimensional Cutting Gap in Electrochemical Machining", ASME Transaction, J. of Engineering for Industry, pI 00 (1969)

11.

"Electrochemical Machining., Prediction and Correlation of Process Variables", AS ME Transactions, J. of Engineering fot Industry, 88:455-461, (1966)

12.

"Laminar Two-Phase Boundary Layers in Subcooled Liquids", J. of Applied Mathematics and Physics (ZAMP), 15, 388*399 (1964)

J3.

"Onset of Stable Film Boiling and the Foam Limit", Intemationalj. of Heat Transfer and Mass Transfer, 6; 987-989 (1963) ) (co-author) 14 "Operating Conditions of Bubble Chamber Liquids", The Review of Scientific Instruments, 34, 308*309. (1963); co-author

15.

"Similar Solutions of the Turbulent Free Convention Boundary Layer for an Electrically Conducting Fluid in the Presence ofa Magnetic Field,"AlAA. J. 1:718-719 (1965)

Not Peer Reviewed (Recent Publications Only)

I. New Fiber Optic Based TechDology for Automatic Tank Gauging ( ATG). NPRA - 2006 Reliability and Maintenance Conference, May 23-26. San Antonio, TX

2. Automatic Tank Gauging: A New Level of Accuracy; A New Device Promises Greater

. Accuracy for Custody TUBsler by Combining Fiber-Optic Seasing with a Pressure.

Sensors Magazine, 12/01106

3. PlasticOptical Fibers Sensors for' Industrial Process Controls and EDvironmental Monitoring,POF World West 2007, June 25-27. 2007 List of PateBts

1. Automatic Shut-Off Valve for Liquid Storage Tanks, 5,522,415

2. Method and Apparatus for Detecting the Presence of Fluids, 5,200,615

3. Sensors For Detecting Leaks, 5,187,366

4. Method for Monitoring Thinning of Walls and Piping Components 4,922,74

5. Method for Monitoring Thinning of Pipe Walls, 4,779,453

6. Looped Fiber Optic Sensor for the Detection of Substances (5,828,798)

7. Coated Fiber Optic Sensor for The Detection of Substances (5,982,959)

8. Method arid Apparatus for Analyzing Infonnation of Sensors Provided Over Multiple

. Waveguides (6,870,607)

Honors

1. Engineer of Distinction - PUblished by Enginee~ Joint Council

2. American men and Women in Science

3. The Blackwall Award for Machine Tools

4. Member Sigma*Xi Professional Activities I. Reviewed papers for the ASME Journal and the Journal of Sensors and Actuators

2. Taught a class on Diesel Engines at Montiomery College, Rockville, MD.

3. Served as a member of a Railroad Committee that development 8 standard for locomotive Fueling

4. Funded and sponsored research and development work at the Engineering Department of the University of Virginia. The research produced a novel method of measuring pipe wall thinning from erosion/corrosion