ML14118A359

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Statement of Professional Qualifications of Kenneth J. Karwoski, Attachment a
ML14118A359
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/17/2014
From: Karwoski K
Division of Engineering
To:
NRC/OCM
SECY RAS
References
50-389-LA, License Amendment, RAS 25866
Download: ML14118A359 (5)


Text

April 17, 2014 Karwoski Statement of Professional Qualifications Kenneth J. Karwoski Senior Level Advisor for Steam Generator Integrity and Materials Inspection Division of Engineering Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Summary Mr. Kenneth J. Karwoski, is the Senior Level Advisor for Steam Generator Integrity and Materials Inspection in the Division of Engineering, Office of Nuclear Reactor Regulation, U.S.

Nuclear Regulatory Commission (NRC), in Washington, District of Columbia (DC). His academic credentials include a Bachelors of Science degree in chemistry and a Bachelor of Science degree in computer science. Mr. Karwoski also qualified as an Engineering Officer of the Watch in the U.S. Navys nuclear power program. His technical background includes extensive involvement in several materials engineering issues related to safe nuclear power plant operations including welding and steam generator integrity issues. Mr. Karwoski has numerous publications and has extensive experience in making presentations to a variety of technical and public audiences, including the Advisory Committee on Reactor Safeguards. Mr.

Karwoski has been a participant in the American Society of Mechanical Engineers (ASME)

Working Group on Welding and Special Repair Processes, the subgroup on Repair and Replacement Activities, and the Board on Nuclear Codes and Standards. Mr. Karwoski is also the NRCs Dam Safety Officer and represents the NRC on the Interagency Committee on Dam Safety.

Education:

Wayne State University (Detroit, Michigan), Chemistry, BS, 1985 University of Maryland University College (College Park, Maryland), Computer Science, BS, 1993 Experience:

United States Nuclear Regulatory Commission July 2001 to Present:

Senior Level Advisor for Steam Generator Integrity and Materials Inspection Division of Engineering / Office of Nuclear Reactor Regulation This position involves providing advice and guidance to management, division and higher, related to steam generator integrity issues. My official responsibilities include the technical, safety, and regulatory compliance reviews of a variety of steam generator submittals. I provide advice to management, supervisors and staff to support the activities of the division, including review of license renewal applications. This included providing advice and guidance to the staff related to adoption of new steam generator technical specification requirements contained in TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, and TSTF-449, Revision 4, Steam Generator Tube Integrity. It also included preparing U.S. Nuclear Regulatory Commission Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, to facilitate adoption of these new technical specification requirements at all pressurized water reactors in the U.S. and 1

April 17, 2014 Karwoski peer reviewing/reviewing most of the plant-specific submittals adopting these new technical specification requirements.

January 2001 to July 2001 Assistant Branch Chief Engineering Research and Applications Branch / Office of Nuclear Regulatory Research This position included supervising a multi-disciplined group of approximately 15 engineers and scientists responsible for research in the areas of mechanical, civil, structural, geotechnical, and electrical (instrumentation and control) engineering.

April 2000 to October 2000 Acting Assistant Branch Chief Materials Engineering Branch / Office of Nuclear Regulatory Research This position included supervising approximately 15 individuals responsible for evaluating issues associated with pressurized thermal shock, environmentally assisted corrosion, steam generator tube integrity, electrical engineering (cable degradation), and dry cask integrity.

April 1999 to April 2000 and October 2000 to January 2001 Technical Assistant Division of Engineering / Office of Nuclear Reactor Regulation This position involved assisting the Division Director on administrative and technical tasks including developing and implementing an Operating Plan for use by Division management.

This position also involved coordinating and developing the Divisions response on various generic licensing and policy issues.

October 1991 to April 1999 Materials Engineer Materials and Chemical Engineering Branch / Office of Nuclear Reactor Regulation This position involved reviewing plant-specific steam generator tube integrity issues. In addition, it involved writing or being a significant contributor to Information Notices and Generic Letters that informed stakeholders of recent events and trends. This position also involved providing guidance to junior members of the branch, briefing senior management on safety-significant issues, and participating in NRC inspection activities of licensees steam generator tube inspections.

DuPont August 1990 to October 1991 Area Consultant Deepwater, New Jersey 2

April 17, 2014 Karwoski This position involved ensuring product quality met customer specifications and supervising numerous technical projects. The primary focus was making my business unit more cost effective while maintaining safety. Specific projects included upgrading analog instrumentation to digital, improving the mechanical utility of a waste water treatment system, developing the design for dilution facilities and chemical emissions control systems, developing techniques for operators use to ensure optimal performance of the product line, and designing and constructing a waste water treatment system.

U.S. Navy Lieutenant July 1984 to June 1990 This position involved serving as the Chemistry and Radiological Controls Assistant and Main Propulsion Assistant on-board a nuclear submarine and supervising approximately 35 highly trained technical specialists in both a refueling overhaul and operational environment ensuring the proper operation and maintenance of the reactor coolant system, steam generating system, steam propulsion plant, and associated auxiliaries. Specific accomplishments included revising and writing numerous technical procedures, supervising the initial criticality of a new reactor core in a highly scrutinized and political environment, directing at-sea testing of propulsion plant equipment following a refueling overhaul, and formally instructing and certifying all mechanical watchstanders.

Honors/Awards:

NRC Performance Awards: 2014, 2013, 2012, 2011, 2010, 2009, 2008, 2007, 2006, 2004, 2003, 2002 NRC High Quality Increase / Special Act Awards: 2007, 2006, 2004, 1998 (2), 1996, 1994, 1992 Certificates of Appreciation: 2012 U.S. Navy Achievement Medal: 1990 Commander Submarine Group Six Commendation: 1989 Admiral A.I. McKee Award: 1987 Publications:

Author, co-author, peer reviewer of numerous NRC reviews/documents, including:

NUREG-1841, U.S. Operating Experience with Thermally Treated Alloy 690 Steam Generator Tubes, August 2007 NUREG-1771, U.S. Operating Experience with Thermally Treated Alloy 600 Steam Generator Tubes, April 2003 NUREG-1604, Circumferential Cracking of Steam Generator Tubes, April 1997 U.S. Nuclear Regulatory Commission Regulatory Issue Summary 2009-04, Steam Generator Tube Inspection Requirements, April 3, 2009, ML083470557 3

April 17, 2014 Karwoski U.S. Nuclear Regulatory Commission Regulatory Issue Summary 2007-20, Implementation of Primary-to-Secondary Leakage Performance Criteria, August 23, 2007, ML070570297 U.S. Nuclear Regulatory Commission Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 2006, ML060200385 U.S. Nuclear Regulatory Commission Generic Letter 2004-01, Requirements for Steam Generator Tube Inspections, U.S. Nuclear Regulatory Commission Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes, April 28, 1995 U.S. Nuclear Regulatory Commission Information Notice 2013-20, Steam Generator Channel Head and Tubessheet Degradation, October 3, 2013, ML13204A143 U.S. Nuclear Regulatory Commission Information Notice 2013-11, Crack-Like Indications at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes, July 3, 2013, ML13127A236 U.S. Nuclear Regulatory Commission Information Notice 2012-07, Tube-to-Tube Contact Resulting in Wear in Once-Through Steam Generators, July 17, 2012, ML120740578 U.S. Nuclear Regulatory Commission Information Notice 2010-21, Crack-Like Indication in the U-Bend Region of a Thermally Treated Alloy 600 Steam Generator Tube, October 6, 2010, ML102210244 U.S. Nuclear Regulatory Commission Information Notice 2010-05, Management of Steam Generator Loose Parts and Automated Eddy Current Data Analysis, February 3, 2010, ML093640691 U.S. Nuclear Regulatory Commission Information Notice 2008-07, Cracking Indications in Thermally Treated Alloy 600 Steam Generator Tubes, April 24, 2008, ML080040353 U.S. Nuclear Regulatory Commission Information Notice 2007-37, Buildup of Deposits in Steam Generators, November 23, 2007, ML072910750 U.S. Nuclear Regulatory Commission Information Notice 2005-09, Indications in Thermally Treated Alloy 600 Steam Generator Tubes and Tube-to-Tubesheet Welds, April 7, 2005, ML050530400 U.S. Nuclear Regulatory Commission Information Notice 2004-16, Tube Leakage Due to a Fabrication Flaw in a Replacement Steam Generator, August 3, 2004, ML041460357 U.S. Nuclear Regulatory Commission Information Notice 2004-10, Loose Parts in Steam Generators, May 4, 2004, ML041170480 U.S. Nuclear Regulatory Commission Information Notice 2002-02, Supplement 1, Recent Experience with Plugged Steam Generator Tubes, July 17, 2002, ML021980191 4

April 17, 2014 Karwoski U.S. Nuclear Regulatory Commission Information Notice 2002-02, Recent Experience with Plugged Steam Generator Tubes, January 8, 2002, ML013480327 U.S. Nuclear Regulatory Commission Information Notice 9749, "B&W Once-Through Steam Generator Tube Inspection Findings," July 10, 1997 U.S. Nuclear Regulatory Commission Information Notice 9638, "Results of Steam Generator Tube Examinations," June 21, 1996.

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