Curriculum Vitae for Dr. Joram (Joe) Hopenfeld

Curriculum Vitae for Dr. Joram (Joe) Hopenfeld
SUMMARY OF DIRECT EXPERIENCE RELATING TO THE INTEGRITY OF
THE RPVs at Doel 3 and Tihange 2
• Drafted a Legal Briefs to the NRC in connection with life extensions for the
Vermont Yankee and Indian Point Reactors. Major issue was fatigue life of
reactor vessel (RPV)
• Steam Generator Degradation Monitoring.
• Drafted legal briefs regarding the fatigue damage to the steam generators at
the San Onofre Plant (2013)
• Erosion/Corrosion, FAC (relevant to the SG feed ring failure at the San
Onofre plant (1992)
• Safety Consequences of Steam Generator Tube Failures,
• Iodine transport and Spiking,
• POD of crack detection by Eddy Current,
• Metal Fatigue from Thermal Transients (PWRs and BWRS)
• Evaluate Indian Point Reactor Vessels (RPVs) integrity under pressurized
thermal shock events (PTS)
• Identified safety issues with connection of SG tube degradation. Consequent
he NRC launched a steam Generator Action Plan which resulted in the
formulation of the latest SG performance criteria
• Vibrations in BWR dryers.
• Managed a major International program, MB-2 (US, UK, EPRI ) on steam
generator performance during design basis accidents.
• Conducted sensitivity studies with the RELAP computer code on operator’s
ability to keep the SG inventory at mid level as a function of the number
ruptured tubes.
• Conducted studies on jet erosion as a potential for leakage increase during SG
accidents.
• Conducted numerical studies on SG tube ruptures during severe accidents
• Designed, fabricated and field tested instrumentation for a very harsh
vibration environment.
• Holds several patents on methods for monitoring wall thinning
• Managed the development of acoustic leak detection systems for LMFBR
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
steam generators.
• Testified in before Congressman DeFazio regarding steam generator
degradation at the Trojan Nuclear reactor
A. Professional Expertise
Nuclear safety, fracture mechanics, thermal hydraulics, corrosion and instrumentation
for power plants and environmental monitoring.
B. Current Activities
Nuclear Safety Consultant
C. Qualifications
• Engineering, University of California at Los Angeles: BS 1960, MS 1962, Ph.D 1967. Major field of studies: Heat Transfer and Mass Transfer, Fluid Dynamics and Electrochemistry • I have 50 years of experience in industry and government primarily in the areas of steam generator performance, thermal-­‐hydraulic, and material testing in nuclear and fossil power plants. My major activities were focused on corrosion/erosion, thermal hydraulics Sodium Cooled Nuclear Power Plants , Pressurized Water Reactors, (“PWRs”) and in Coal Fired Plants. I have 2
Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
managed a major international program on steam generator performance during accidents involving various thermal transients in PWRs. • As a result of my work at the Nuclear Regulatory Commission, (“NRC”) my position regarding the safety implication of steam generator tube degradation was adopted. Consequently, in 2001 the NRC launched the STEAM GENERATOR ACTION PLAN, SGAP (NRC web site) to address the various safety issues that I have raised in a series of documents starting 1992, known as the DPO. In September 2007 the NRC issued s a new performance technical requirement specification s, TS, to reduce the risk from accident induced tube ruptures and tube ruptures during normal operations, • I made numerous presentations to the Atomics Safety Licensing Board ( ASLB ) and the Advisory Committee on Reactor Safety (ACRS) on the following issues : Erosion/Corrosion ( FAC), Steam Generator Degradation Monitoring, Safety Consequences of Steam Generator Tube Failures, Metal Fatigue -­‐ PWRs and BWRS, and Vibrations in BW dryers. • In 2013 I discovered a major error in the Mitsubishi fatigue damage calculations for the San Onofre steam generators. The San Onofre Plant was retired following the presentation of these results to the NRC. 3
Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
• I was the owner and CEO of a small Maryland startup company, Noverflo, Inc, for the development developing fiber optic and corrosion sensors for the oil & gas, the transportation, and the environmental monitoring industries. . • I have published 14 papers in peer-­‐reviewed technical journals in the areas of thermal-­‐hydraulics, corrosion, erosion, steam generator dose releases during accidents, steam explosions, sensors and ECM machining. I hold eight US patents and I am listed in the Engineers of Distinction published by the Engineers Joint Council and in American Men and Women in Science. D. Summary of Work Experience
Self-Employment 1992-Present
a. Consulting Activities 2001- Present
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-10 Research and Education Foundation
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
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 Corporation, 2005 and 2013
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.
Provided testimony to the CPUC in connection with cost to the rate payer as a result of
the damages to the San Onofre steam generators in 2012
4. New England Coalition, 2005-2007
Preparation and presentation of material to the ASLB in connection with the life
extension of the Vermont Yankee Nuclear Plant
5. Riverkeepers (Jointly with the State of New York) 2007 -Present
Preparation and presentations of material to the ASLB in connection with the life
extension of the Indian Point Nuclear Plant in New York
6. Friends of the Earth, FoE, April 2013-June 2013
Drafted reply to Southern California Edison SCE “ no significant hazards consideration “
requesting NRC approval for continuing San Onofre operation. The reply pointed out
that AREVA, Westinghouse, and Mitsubishi all faile to account for the fatigue damage
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
that the steam generators suffered during their first cycle of operations. SCE promptly
retired the plant before the NRC issue their ruling on the case.
Self-Employed - 1992-2012
CEO , Noverflo, Inc -Development and commercialization of corrosion sensors , liquid
level monitors, and shut off valves for the oil and gas industry.
• Developed and commercialized a shutoff valve for fuel tanks to comply with new EPA regulations (1992-­‐2000) • Completed, a USDOE sponsored program for the development of a novel system for automatic tank gauging. • Sponsored experimental and analytical studies for the feasibility of online remote
monitoring of corrosion/erosion at the University of Virginia.
• Installed On-Line wall pipe wall thinning monitors at an Arizona large copper
mine facility.
Industry and Government
ATOMICS INTERNATIONAL 1962-1971, Canoga Park, Calif.
• Conducted corrosion and fatigue tests on the effect of flowing sodium on internally heated specimen at high heat fluxes. • Conducted tests on small enriched uranium discs in a research reactor on temperature fluctuations during transition film boiling under transients and behavior of two phase boundary layers in sub cooled water 6
Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
• Conducted tests and developed design equations for natural convection flow in buildings during sodium fires. • Conducted theoretical studies on the mixing of fluids with two different initial temperatures. • Conducted tests on small discs in a research reactor on temperature fluctuations during transition film boiling under transients and behavior of two phase boundary layers in sub cooled water • Conducted tests and developed design equations for natural convection flow in buildings during sodium fires. • Conducted theoretical studies on the mixing of fluids with two different initial temperatures. AEC, ERDA DOE 1971-82
.
• Evaluated environmental and radiation effects on corrosion, fatigue, fouling in connection with the development of standards for LMFBRs (AEC, Material Branch) • Reviewed standards on coolant chemistry and oxygen monitoring for LMFBRs (AEC, Material Branch • Evaluated Thermal Striping Effect in connection with fuel core assembly designs and mixing tees. (AEC, Component Branch) • Managed experimental studies and participated in the development of equations for flow through cracks in caustic environments under cyclic loads, 7
Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
• Managed Tests and analytical studies on flow /structure interaction and cavitation damage (a form of fatigue damage), thermal striping and fatigue analysis • Managed experimental and numerical modeling of flow mixing and heat transfer in fuel assemblies and heat exchangers. • Managed Tests and analytical studies on flow /structure interaction and cavitation demage (a form of fatigue damage) (AEC, Component Branch). • Responsible for the resolution of issues on erosion/corrosion , NOx/ SOx emissions and instrumentation for high temperature Balance of the Plant Components ( coal fire boilers) • Studied manufacturer ‘s data base on erosion damage from pin hole leaks in adjacent tubes in Kraft Boilers ( pulp and paper plants) • Managed programs on thermal striping in blanket assembles and mixing tees • Managed the developments of Thermal-­‐Hydraulic codes (COBRA) for predicting temperature distribution in fuel assembles for both sodium and water. Nuclear Regulatory Commission, NRC -1982 -2001
• Analyzed the safety consequence of steam generator tube ruptures and other
component failures following Main Steam Line Break and Severe Accidents.
Evaluated the effect of FAC on leak before break licensing. Reviewed NUREG 1570
from the perspective of component aging.
• Conducted an assessment of safety risk significant FAC failures inside steam
generators following the 1987 Surry accident. Visited the Sequoia plant to inspect the
J-tube failures and held discussions with UK regarding their laboratory test results in
considerations of initiating a cooperative program
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
• Evaluate all modes of steam generator tube degradations (corrosion, high cycle fatigue, wear) and the applicable instrumentation (eddy current, fiber optics, acoustics) applicability of cracks growth data from lab test to field conditions in PWR steam generators ( NRC) • Formulated several new issues relating to tube cracking, crack detection and safety consequences following certain transients such as steam line break, tube rupture (SGTR) and station blackouts (SBOs). The NRC designated these issues as a Differing Professional Opinion (DPO). Following the February 2000 tube rupture at IP2, the DPO attracted considerable public interest because the accident was linked to some issues that were originally raised in the DPO. • Managed an international program the thermo-­‐hydraulic response of a full scale PWR steam generator to power transients. • • Investigated and modeled Iodine speciation and partitioning in PWR steam generators. • Conceived and managed a program that obtained data on energy releases from steam explosions in Kraft boilers for .for studying core melts behaviour. PUBLICATIONS IN PEER REVIEWED JOURNALS
1.
2.
3
Distributed Fiber Optic Sensors for Leak Detection In Landfills, Proceeding of
SPIE Vol 3541 (1998)
Continuous Automatic Detection of Pipe Wall Thinning, ASME Proceedings
of the 9th, International Conference on Offshore Mechanics and Arctic
Engineering. Feb. 1990
Iodine Speciation and Partitioning in PWR Steam Generators, Nuclear
Technology, March 1990
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
4.
5.
6.
7.
8.
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10.
11.
12.
13
14.
Comments on "Assessment of Steam Explosion Induced Containment
Failures" Letter to the Editor, Nuclear Science and Engineering, Vol. 103,
Sept. 1989
Experience and Modeling of Radioactivity Transport Following Steam
Generator Tube Rupture, Nuclear Safety, 26,286, 1985
Simplified Correlations for the Predictions of Nox Emissions from Power
Plants. AIAA Journal of Energy, Nov.-Dec., 1979
Grain Boundary Grooving of Type 304 Stainless Steel in Armco Iron Due to
Liquid Sodium Corrosion, Corrosion, 27, No.11, 428, 1971
Corrosion of Type 316 Stainless Steel with Surface Heat Flux in 1200 Flowing
Sodium, Nuclear Engineering and Design, 12; 167-169, 1970
Prediction of the One Dimensional Cutting Gap in Electrochemical Machining,
ASME Transaction, J. of Engineering for Industry, p100 (1969)
Electrochemical Machining- Prediction and Correlation of Process Variables,
ASME Transactions, J. of Engineering for Industry, 88:455-461, (1966)
Laminar Two-Phase Boundary Layers in Subcooled Liquids, J. of Applied
Mathematics and Physics (ZAMP), 15, 388-399 (1964)
Onset of Stable Film Boiling and the Foam Limit, International j. of Heat Transfer
and Mass Transfer, 6; 987-989 (1963) ) (co-author)
Operating Conditions of Bubble Chamber Liquids, The Review of Scientific
Instruments, 34, 308-309. (1963); co-author
Similar Solutions of the Turbulent Free Convention Boundary Layer for an
Electrically Conducting Fluid in the Presence of a Magnetic Field, AIAA J. 1:718719 (1965)
LIST OF PATENTS
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 4,922,748
5. Method for Monitoring Thinning of Pipe Walls, 4,779,453
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
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 and Apparatus for Analyzing Information of Sensors Provided Over Multiple
Waveguides (6,870,607)
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026
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Testimony of Dr. Joram Hopenfeld
December 13, 2004
Application 04-02-026