ML072850827

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Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit D, Professional Qualifications of Staff Witnesses, This Exhibit Contains All Statements of Professional Qualifications That Are Also Included in Staff Exhibits B.
ML072850827
Person / Time
Site: Oyster Creek
Issue date: 09/20/2007
From: Ashar H, Jennifer Davis, Hartzman M, Lund A, Kamal Manoly, O'Hara T, Salomon A
Office of Nuclear Reactor Regulation
To:
SECY RAS
References
50-219-LR, AmerGen-Staff-D, RAS 14389
Download: ML072850827 (29)
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Text

Staff Exhibit D Invallow -' c-G L, ofM tby: App~i~lt/Liceflsee Intervenor_______

DOCKETED USNRC October 1, 2007 (10:45am)

OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF PROFESSIONAL QUALIFICATIONS OF STAFF WITNESSES NOTE: This exhibit contains all statements of professional qualifications that are also included in Staff Exhibits B and C. The professional qualifications of A. Louise Lund and Kamal Manoly are also included.

"-Tempca1/2 X--,V-rY- 0a7 C

Hansraj G. Ashar Statement of Professional Qualifications CURRENT POSITION:

Senior Structural Engineer Division of Engineering, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Rockville, MD EDUCATION Bachelor of Civil Engineering, Gujarat University, India Masters Degree in Civil-Structural Engineering, 1958, University of Michigan, Ann Arbor, MI Registered Professional Engineer in the States of Ohio and Maryland.

EXPERIENCE For the last 33 years, I have been working as a Structural engineer/Sr. Structural Engineer with the U.S. Nuclear Regulatory Commission in review of the plant licenses, standards development, containment related research activities and license renewal activities.

For the first eleven years of my career, I have worked as a Bridge Engineer in the States of Ohio, New Jersey; and in Wiesbaden Germany on designing steel, reinforced and prestressed concrete bridges. The next five years, I worked as a Lead Civil Engineer on developing design documents and procurement specifications for nuclear power plants, namely, Three Mile Island, Unit 2, Forked River, and Oyster Creek.

I represent NRC in a number of Standards Developing Organizations, namely, American Society of Mechanical Engineers (ASME), American Concrete Institute, and American Institute of Steel Construction on several committees developing standards related to the nuclear power plant structures. I am a fellow member of the American Concrete Institute, and the American Society of Civil Engineers.

REGULATORY DOCUMENTS (Principal Author):

Information Notices IN 93-53 Effects of Hurricane Andrew on Turkey Point Nuclear Generating Station and Lessons Learned, April 1994 IN 95-49 Seismic Adequacy of Thermo-Lag Panels, October 1995 Supplement 1: Seismic Adequacy of Thermo-Lag Panels, December 1997 IN 97-10 Liner Plate Corrosion in Concrete Containments, March 1997 IN 97-11 Cement Erosion from Containment Subfoundation at Nuclear Power Plants, March 1997

IN 97-22 Failure of Welded Steel Moment-Resisting Frames During the Northridge Earthquake, April 1997 IN 97-29 Containment Inspection Rule, May 1997 IN 98-26 Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundation, July 1998 IN 99-10 Degradation of Prestressing Tendon Systems in Prestressed Concrete Containments, April 1999 IN 06-01 Torus Cracking in a BWR Mark-I Containment, January 2006 ISG 06-01 Aging Management Program for Inaccessible Areas of BWR Mark-I Containment Drywell shell, September 2006 Inspection Procedures IP 62002 Inspection of Structures, Passive Components, and Civil Engineering Features at Nuclear Power Plants, Dec. 1996 IP 62003 Inspection of Steel and Concrete Containments at Nuclear Power Plants, June 1997 Regulatory Guides RG 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments. Rev. 1 (1974), 2 (1976), 3 (1990)

RG 1.35.1 Determining Prestressing Forces for Inservice Inspection of Prestressed Concrete Containments: Draft (1979), final (1990)

RG 1.90 Inservice Inspection of Prestressed Concrete Containments with Grouted Tendons: (1977).

RG 1.107 Qualification of Cement Grouting for Prestressing Tendons in Prestressed Concrete Containments: (1977)

RG 1.136 Materials, Construction and Testing of Concrete Containments (Endorsement of ASME Section III/Div. 2 (or ACI 359): (1981)

RG 1.142 Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments): (1981)

Technical Support to the principal coordinators of 10 CFR 50.55a, (Codes and Standards)

Revisions on endorsing Subsections IWE/IWL (ISI of Containments) of the ASME Code: 1994 to Present

PROFESSIONAL AND COMMUNITY ACTIVITIES Participation in National and International Standards Organizations Member of the following NSO and INSO Committees:

" American Institute of Steel Construction (AISC)

Chairman: Nuclear Specification Committee (A!SC/ANSI N690)

Member: Building Specification Committee Advisory: Seismic Provisions Committee

" American Concrete Institute (ACI) 349 Committees Member: Main committee Member: Subcommittee 1 on General Requirements, Materials and QA Member: Subcommittee 2 on Design

" American Society of Mechanical Engineers (ASME):

Member: Working Group on Inservice Inspection of Concrete and Steel Containments (Subsections IWE and IWL of ASME Section Xl Code)

Member: ASME/ACI Joint Committee on Design, Construction, Testing and Inspection of Concrete Containments and Pressure Vessels

" Member: RILEM Task Committee 160-MLN: Methodology for Life Prediction of Concrete Structures in Nuclear Power Plants

" Member: Federation Internationale du Beton (FIB) Task Group 1.3: Containment Structures

" Consultant to IAEA on Concrete Containment Database (2001 to 2005)

PROFESSIONAL MEMBERSHIPS Professional Engineer: State of Ohio, State of Maryland Fellow - American Concrete Institute Fellow - American Society of Civil Engineers Professional Member - Post-tensioning Institute COMMUNITY ORGANIZATIONS - SERVICES Member- Montgomery County Energy and Air-Quality Advisory Committee (1995 to 2001)

Science Fair Judge (Montgomery County) - 1994-2001 Member-Architectural Committee - Hickory Crest, Columbia, Association Peer reviewer of number of papers to be published in ASCE Material Journal, NED Periodicals, and ACI International.

PUBLICATIONS/PRESENTATIONS

1. Ashar, H., Terao, D., Imbro, E.: "Reliability of Containment and Risk-Informed Decision Making - A Perspective," Presented at SMiRT17 International Conference in Prague, Czech Republic, August 2003.
2. Ashar, H., Imbro, E, Terao, D.: Integrated Leak Rate Testing of Containments - A Regulatory Perspective, Presented by Eugene Imbro at ICONE1 1 in Tokyo, Japan, April 2003.
3. Ashar, H.: Inspection of Containment Structures in the U.S.A. Presented at the 1 6 th International Conference on Structural Mechanics in Reactor Technology, Washington DC. August 12-17, 2001.
4. Kotzalas, M., Ashar, H.: Regulatory Issues Involved in the Use of the ASME XI, IWE/IWL, Presented at the ASME Pressure Vessel and Piping Conference, Atlanta, GA.

July 2001.

5. Ashar H., Kotzalas, M.: Implementation of Containment Inspection Rule, 10 CFR Part 50.55a, Presented at the ASME Pressure Vessel and Piping Conference, Atlanta, GA.

July 2001.

6. Ashar, H.: Implications of Concrete Structure Degradations in Nuclear Power Plants, Proceedings of the International RILEM Conference on Life Prediction and Aging Management of Concrete Structures, Cannes, France, October 16-18, 2000.
7. Ashar, H., Bagchi, G.: "Monitoring Degradation of Concrete Structures in U.S. Nuclear Power Plants," Proceedings of the 8 th International Conference (Sponsored by RILEM) on "Life Management and Aging Management of Concrete Structures," Bratislava, Slovakia, July 1999.
8. Ashar, H., Bagchi, G.: "Implementation of Maintenance Rule for Structures,"

Proceedings of the 7" symposium on Current Issues Related to Structures, Systems, and Piping, North Carolina State University, Raleigh, NC, December 1998 (Published in Nuclear Engineering and Design in Nov. 1999).

9. Ashar, H., Costello, J., Graves, H.: "Prestress Force Losses in Containments of U.S.

Nuclear Power Plants," Proceedings of the Joint WANO-PCIOECD-NEA Workshop on Prestress Loss in Nuclear Containments, Poitier, France, August 1997.

10. Ashar, H., Bagchi G.: "Safety Related Nuclear Power Plant Structures - Assessment of Inservice Conditions," NUREG 1522, U.S. Nuclear Regulatory Commission, Washington D.C., 20555, May 1995.
11. 'Ashar, H., Jeng, D.: "Degradation of Passive Components in U.S. Nuclear Power Plants," Proceedings of the 6th Symposium on Current Issues Related to Structures, Systems, and Piping, North Carolina State University, Raleigh, NC, December 1996.
12. Ashar, H., Jeng, D.: "Performance of Structures in Nuclear Power Plants," Paper X/2, Proceedings of the 5th Symposium on Current Issues Related to Structures, Systems, and Piping, Orlando, Fl., December 1994.
13. Ashar, H., Naus, D., Tan, C. P.: "Prestressed Concrete in U.S. Nuclear Power Plants,"

Concrete International, American Concrete Institute, Detroit, Michigan, Part I in May 1994, Part 2 in June 1994.

14. Jeng, D., Bagchi, G., Ashar, H.: "Structural Issues Related to Containment Performance in Advanced Reactors," Proceedings of the Second ASME/JSME Conference on Nuclear Engineering, San Francisco, CA, March 1993.
15. Ashar, H., Tan, C. P.: "Inservice Performance of Containment Structures - U.S.

Experience," Proceedings of the 1 1 th Conference of Structural Mechanics in Reactor Technology (SMIRT), Tokyo, Japan, August 1991.

16. Tan, C. P., Ashar, H.: "Modifications of Concrete Containments for Steam Generator Replacement-Regulatory Considerations," Proceedings of SMIRT 11 th, Tokyo, Japan, August 1991.
17. Ashar, H., Jeng, D.: "Effectiveness of Inservice Requirements for Prestressed Concrete Containments," Proceedings of the 2nd International Conference on Containment Design and Operation, Toronto, Ontario, Canada, October 1990.
18. Ashar, H., Degrassi, G.: "Design and Analysis of Free standing Spent Fuel Racks in Nuclear Power Plants," Proceedings of the 1 0 th SMIRT Conference, Anaheim, CA.,

August 1989.

19. Bagchi, G., Jeng. D., Ashar, H.: "Proposed Modifications of NRC's Standard Review Plan for Seismic Analysis," Proceedings of the 2 nd Symposium on Current Issues Related to NPP Structures, Systems, and Piping, Orlando, Fl., Dec. 1988.
20. Ashar, H., Jeng, D.: "Spent Fuel Storage - A Regulatory Perspective," Presented at 1988 ASME Joint Power Generation Conference, Philadelphia, Pa. September 1988.
21. Richardson, J., Ashar, H.: "Regulatory Perspective on Containment Performance,"

Presented at MITI/NRC Conference on Nuclear Technology, Tokyo, Japan, Dec. 1987.

22. Ashar, H., Naus, D.: "Overview of the Use of Prestressed Concrete in U.S. Nuclear Power Plants," Nuclear Engineering and Design, Val. 75, North Holland Publishing Company, August 1983.
23. Dougan, J., Ashar, H.: "Evaluation of Grease Performance in Prestressed Concrete Containments," Proceedings of 6 th SMIRT Conference, Chicago, 11. August 1983.

James A. Davis, Ph. D Statement of Professional Qualifications CURRENT POSITION:

Senior Materials Engineer Division of License Renewal, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Rockville, MD EDUCATION:

B. Met. E., The Ohio State University, 1965, Metallurgical Engineering M.S., The Ohio State University, 1965, Metallurgical Engineering Ph.D., The Ohio State University, 1968, Metallurgical Engineering

SUMMARY

Over 39 years of experience in material engineering with over 20 years of experience in the nuclear power industry. Significant experience in the following areas:

  • Materials Engineering
  • Corrosion and Control
  • Welding and Special Repair Processes

" Nuclear Facilities Audits

  • Allegations
  • Reviews of Navy Submarine Power Plant Designs

" Quality Assurance

" ASME Code Committees

" ASTM D-33 Committee on Coatings for Power Generation Facilities EXPERIENCE:

U.S. Nuclear Regulatory Commission, 11/11/1990 - Present 11/13/2005 to Present - Senior Materials Engineer, Division of License Renewal, Office of Nuclear Regulatory Research

  • Audit Team Leader for the license renewal safety audit at the Pilgrim Nuclear Power Station
  • Audit Team Member for the license renewal safety audit at the Oyster Creek Generating Station

12/15/2001 - 11/13/ 2005 - Senior Materials Engineer in the Division of Engineering Technology, Office of Nuclear Regulatory Research

  • Program Manager on the Steam Generator Tube Integrity Program overseeing work conducted at Argonne National Laboratory

" Acting Program Manager for Non-Destructive Examination research at Pacific Northwest National Laboratory 11/11/1990 - 12/15/2001 - Technical Reviewer in the Materials and Chemical Engineering Branch, Chemical Engineering and Metallurgy Section, Division of Engineering, Office of Nuclear Reactor Regulation.

  • chemical decontamination,

" Boiling Water Reactor internals cracking,

  • pump and valve internals cracking,
  • pipe integrity issues,

" corrosion behavior for dry cask storage, and interaction of coatings with spent fuel water,

" Coordinated the responses to a generic letter on containment coatings for nuclear power plants.

" NRC representative to ASTM D-33 on coatings for power generation facilities.

  • Member of the Board of Directors for the National Board of Registration for Nuclear Safety Related Coating Engineers & Specialists.
  • Member of ASME on Welding and Special Repair Processes.
  • Member of an Augmented Inspection Team at Palisades on fuel handling problems, Point Beach on the hydrogen burn as a result of interactions between borated water and the inorganic Zinc coating during dry cask loading operations and Davis-Besse on the Boric acid corrosion of he vessel head.

" Contract Technical Monitor and Project Officer for numerous contracts at Brookhaven National Labs.

0 Technical reviewer for the design of the Navy Seawolf Submarine and the Virginia Class Submarine

  • Reviewer on the DOE project to produce tritium in a commercial reactor (Watts Bar)
  • Numerous presentations to senior NRC management including the Chairman, the Executive Director for Operations, the Committee to Resolve Generic Issues, and the Advisory Committee on Reactor Safety and Safeguards.
  • Testified before Representative Dingle's staff on the safety of fasteners in nuclear power plants as a result of concerns raised by a private citizen.

Polyken Division of the Kendall Company. Senior Research Associate, 1981 -1990:

Responsible for Technical Marketing for the pipeline coating division providing technical data and reports to domestic and international customers. Company representative to the National Association of Corrosion Engineers, the American Water Works Association coatings committees, and ASTM coating committees.

Arthur D. Little, Senior Consultant, 1979 - 1981:

Consultant to DOE on Defense Nuclear Waste issues and Waste Tank corrosion issues.

Consultant on numerous commercial contracts on corrosion, coating, metallurgical, and plating issues.

Allied Tube and Conduit Corp., Director of Research, 1978-1979:

Responsible for research and development for metallurgical tube forming, welding, chemical cleaning of steel, galvanizing, surface treatment and coating of electrical conduit, fence posts, and specialty tubing. Responsible for Quality Assurance and Process Control.

Allegheny Ludlum Steel Corp., Research Specialist, 1976-1978:

Responsible for customer service for use of stainless steels. in corrosive service.

Responsible for conducting failure analysis. Conducted research on corrosion mechanisms for stainless steels.

Bell Aerospace Company, Senior Research Scientist, 1970-1976:

Program Manager on numerous Navy sponsored programs involving corrosion of aluminum alloys, stainless steels, and titanium alloys in high velocity sea water for the Navy's high performance ships program. Conducted research on corrosion fatigue, stress corrosion, and fouling in sea water. Conducted research on the compatibility of

rocket fuels and oxidizers with fuel handling equipment.

U.S, Steel Corporation. Senior Research Engineer, 1968-1970:

Conducted research on the mechanism of pitting/crevice corrosion, stress corrosion cracking, hydrogen embrittlement, and intergranular corrosion using electrochemical techniques, transmission electron microscopy, optical microscopy, and scanning electron microscopy.

Mark Hartzman, Ph. D.

Statement of Professional Qualifications CURRENT POSITION:

Senior Mechanical Engineer Mechanical and Civil Engineering Branch (EMCB)

Division of Engineering Office of Nuclear Reactor Regulation EDUCATION:

  • B.S. Mechanical Engineering, The City College of New York, New York, N. Y., 1959.
  • MS Mechanical Engineering, University of Washington, Seattle, WA, 1963. Major:

Engineering Mechanics.

  • Ph. D., Mechanical Engineering, University of California, Davis, CA, 1970. Major:

Engineering Mechanics.

SUMMARY

Over 48 years of experience in Engineering Mechanics and Structural Analysis. Over 32 years experience in Nuclear Regulatory review and evaluation. Significant review experience in the following areas:

0 Finite element analysis - solid mechanics, statics and dynamics

  • Structural seismic analysis methodology
  • Structural computer programs

U.S. Nuclear Regulatory Commission, 06/75 - present Wide variety of assignments over this time period. Representative assignments have consisted or consist of the following:

Review of a wide variety of license amendment requests, requiring in-depth technical evaluation of licensee calculational methodology and procedures.

Evaluation of licensee responses to I&E Bulletin 79-07, "Seismic Stress Analysis of Safety Related Piping." Co-author of reports NUREG/CR 1677, "Piping Benchmark Problems", Volumes 1 and 2.

Development of acceptance criteria for I&E Bulletin 79-02, "Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts."

0 Evaluation of license renewal requests in the area of time limited aging analysis of ASME Section III metal components (metal fatigue) for the following plants:

Palisades, St. Lucie Browns Ferry, V. C. Summer Brunswick, ANO-2 0 Evaluation of allegations:

Example: Deficiencies in piping and base plate design at the Diablo Canyon NPP, 1982-1984.

Revision and updating of the Standard Review Plan within the scope of the EMCB.

Evaluation of ASME Section III code cases for acceptance and listing in Regulatory Guide 1.84.

Assistance to NRC Regions with technical resolution of inspection reports and differing professional opinions (DPOs):

Example: Fermi HVAC duct safety under tornado loading. Resulted in NRC Regulatory Issue Summary (RIS) 2006-23, "Post-tornado Operability of ventilating and Air Conditioning Systems Housed in Emergency Diesel generating Rooms."

Example: In 2006, as a member of a Region II Differing Professional Opinion DPO panel, performed the technical evaluation of a DPO regarding Oconee pipe whip structural integrity.

Participation in ASME Section III Code working groups and committees since 1974. As the NRC representative, participated or currently participate in the following groups:

Task Group on Faulted Conditions Working Group on Dynamic and Extreme Loading Conditions Working Group on Vessels (current)

Working Group on Methods Development (current)

The Lawrence Livermore National Laboratory, Livermore, CA, 1973-1975 (On loan to the USAEC, Mechanical Engineering Branch (MEB))

" Review of new plants construction license applications.

" Assistance with development of the Standard Review Plan within the scope of

the MEB.

0 Review of ASME Code Section III faulted condition acceptance criteria.

The Lawrence Livermore National Laboratory, Livermore, CA, 1963-1973.

Computer-based design and analysis of equipment used in testing of nuclear weapons.

Ph. D. dissertation based on this work.

The Boeing Company, Seattle, WA, 1959 - 1963

  • Design and stress analysis of pilotless aircraft and helicopter engines.
  • Research in the fabrication of aircraft components using explosives. MS thesis based on this work.

Timothy L. O'Hara Statement of Professional Qualifications CURRENT POSITION:

Reactor Inspector U.S. Nuclear Regulatory Commission, Region 1 Office, Division of Reactor Safety, Plant Support Branch 2 EDUCATION:

Bachelor of Science in Physics, 1970, Saint Francis University, Loretto, PA U.S. Naval Officer Candidate School, 1971, Newport, RI U.S. Naval Nuclear Power Program, 1972, Bainbridge, MD and Windsor, CT Master of Science in Engineering Management, 1980, University of Pittsburgh, Pittsburgh, PA Master of Business Administration, 1988, Temple University, Philadelphia, PA EXPERIENCE:

U.S. Nuclear Regulatory Commission, June 2002 - Present Reactor Inspector, Region I, Plant Support Branch 2, King of Prussia, PA, October 2005 to Present Conduct engineering inspections and assess licensee performance at commercial nuclear power plants throughout the northeast US. Inspections include Inservice Inspections, Plant Component Replacement Inspections (Steam Generators, Pressurizers, and Reactor Vessel Closure Heads), License Renewal Aging Management Inspections, Plant Modifications, Problem Identification and Resolution, Resident Inspector coverage, and Safety System Design Inspections. Training in ASME Code, Eddy Current Testing, Fracture Mechanics, welding techniques and Construction Procedures.

Reactor Inspector, Region I, En-gineering Branch I, King of Prussia, PA, October 2004 -

September 2005 Conduct engineering inspections and assess licensee performance at commercial nuclear power plants throughout the northeast US. Inspections include Plant Modifications, Problem Identification and Resolution, Fire Protection, In Service Inspection, Resident Inspector coverage, and Safety System Design Inspections. Training in Digital Circuits, Electrical System Coordination and Short Circuit Calculations.

Reactor Inspector, Region I, Electrical Branch, King of Prussia, PA, June 2002 - September 2004 Conduct engineering inspections and assess licensee performance at commercial nuclear power plants throughout the northeast US. Inspections include Plant Modifications, Problem Identification and Resolution, Fire Protection, In Service Inspection, Resident Inspector coverage, and Safety System Design Inspections. Training in BWR and PWR plant design and operation.

Completed the following inspections during the past five years:

Salem U1, Inservice Inspection, September 2004, Team Lead Indian Point U2, Inservice Inspection, November 2004, Team Lead Ginna, Inservice Inspection, March 2005, Team Lead Salem U2, Inservice Inspection, April 2005, Team Lead Beaver Valley U1, Stream Generator Replacement, January - June 2006, Team Lead Beaver Valley, SSDI, August 2002 Calvert Cliffs, Modifications & 50.59 Inspection, December 2002 Vermont Yankee, Modifications & 50.59 Inspection, April 2003 Millstone U2 & U3, Modifications & 50.59 Inspection, June 2003 Nine Mile Point U1 & U2, Modifications & 50.59 Inspection, August 2003 Salem, EDG Turbocharger Special Inspection, September 2003 Fitzpatrick, SSDI, October 2003 Salem U1, Inservice Inspection, September 2003 Ginna, Triennial Fire Protection Inspection, November 2003 Oyster Creek, Triennial Fire Protection Inspection, January 2003 Indian Point U2, Triennial Fire Protection Inspection, January 2004 Vermont Yankee, Triennial Fire Protection Inspection, December 2004 Indian Point U3, Triennial Fire Protection Inspection, February 2005 Ginna, License Renewal Inspection, Scoping & Screening, August 2003 Millstone, License Renewal Aging Management Inspection, September 2004 Indian Point U2, Modifications & 50.59 Inspection, January 2005 Nine Mile Point U1 & U2, License Renewal Aging Management Inspection, February 2005 Oyster Creek, License Renewal Aging Management Inspection, March 2006 Oyster Creek PI&R Team Inspection, May 2004 Hope Creek, PI&R Team Inspection, December 2005 Pilgrim, License Renewal Aging Management Inspection, September 2006 Oyster Creek License Renewal Commitment Inspection, October 2006 Vermont Yankee, License Renewal Aging Management Inspection, February 2007 Calvert Cliffs, PI&R Sample (460v breakers), June 2004 Salem PI&R Sample (CC-17 valve), June 2004 Ginna PI&R Sample (Human Performance), July 2006 Salem PI&R Sample (Auxiliary Building Ventillation - Charcoal Filters), June 2005 Peach Bottom PI&R Sample ( Corrective Actions), July 2006 Salem PI&R Sample (Corrective Actions), September 2006 Oyster Creek, Resident Backfill, July 2003 Salem Resident Inspector Backfill, June 2004 Hope Creek, Inservice Inspection, April 2006 Peach Bottom U2 & U3, PI&R Sample (Torus Corrosion), July 2006 Salem U2 Inservice Inspection, October 2006 Susquehanna U1, Inservice Inspection, March 2007 Salem U1 Inservice Inspection, April 2007

NRC.TRAINING COURSES COMPLETED:

Power Plant Engineering Effective Communication For NRC Inspectors Media Training Workshop Expectations For Inspectors PRA Basics For Regulatory Applications Westinghouse 100 Technology Gathering Information For Inspectors PRA Techniques and Regulatory Perspectives Root Cause/Incident Investigation Workshop Allegations Training - Classroom Ethics Orientation Conducting Inspections GE BWR/4 Technology GE BWR/4 Advanced Technology GE BWR/4 Simulator Field Techniques And Regulatory Processes Ethics Laws & Rules For Employees Fire Protection For Power Plants Response Technical Manual Training SNE 594, Westinghouse Station Nuclear Engineers Training Improving Employment Applications Industrial & Commercial Power Distribution Systems Digital I & C Training Low Voltage Protection Course Eddy Current Testing Eddy Current & UT Testing of RV Head Penetrations, Wesdyne GE BWR/4 Simulator Refresher Training American Concrete Institute Seminar, Inspecting Concrete Structures Fracture Mechanics Training Construction Inspector Training ASME B&PV Code,Section VIII Denton Vacuum, LLC, June 1997 to February 2002 Operations Manager, Vacuum Equipment Division, Moorestown, NJ Responsible for material management, manufacturing, assemble and testing of complex vacuum deposition (thin film) equipment and systems for this privately held company.

Scott Specialty Gases, September 1993 to January 1997 General Manager, High Pressure Technology - Plumsteadville, PA Total business responsibility for the turnaround of high pressure cylinder manufacturing and startup of a custom equipment product line. Establishment of specialty innovative, custom gas handling and distribution equipment. Sales, manufacturing, new product development, and customer service responsibility.

Westinghouse Electric Corporation, December 1975 to August 1993 District Manager, Philadelphia Operations Center - 1989-1993 Total business responsibility for the Engineering Services Division's Philadelphia Region.

Performed commercial electrical services and electrical equipment installation. Responsible for sales, customer service, and engineering services for all industrial sectors.

Manager, Nuclear Services Operations, Moorestown, NJ - 1985-1989 Total P&L responsibility for custom manufacturing decontamination and mobile cleaning services. Directed a staff of 5 managers and 150 technicians. Integrated an acquired subsidiary company into an existing corporate division.

Manager, Mechanical Projects, Monroeville, PA - 1981-1985 Field Service responsibility for reactor internals repairs for commercial power plants. Split pin replacement, reactor upflow conversion, spent fuel rack replacement, foreign object search and retrieval, and miscellaneous mechanical repairs. Extensive work with utility representatives, Westinghouse Engineering and research groups. Managed 22 field engineers and 75 field service technicians Site Manager, Steam Generator Replacement, Surry, VA - 1979-1981 Westinghouse site representative for SG replacement. Responsible for daily contact between utility and Westinghouse engineering, manufacturing and field service resources. Extensive involvement in mechanical problems, welding issues, and plant startup.

Nuclear Fuel Licensing Engineer, Monroeville, PA - 1977 -1979 Lead the Westinghouse effort on reload core licensing. Extensive involvement with utilities and internal Westinghouse Fuel and Engineering Divisions.

Senior Field Service Engineer, Churchill, PA - 1975-1977 Conducted SG eddy current inspections, SG sludge lancing, and SG weld repairs at Westinghouse commercial nuclear power plant. Extensive work with utility representatives and Westinghouse Engineering and Research groups.

U. S. Navy, September 1970 to November 1975 Completed Navy Basic Training and Electronic Technician Class A Training. Attended Officer Candidate School and Naval Nuclear Power Training. Served as a junior engineering office on board USS Seahorse and USS Sam Houston. Served as Electrical Officer, Damage Control Assistant, Ship's Diving Officer, Subsafe Officer, Engineering Plant Watch Officer. Completed extensive ship overhaul and refueling.

PROFESSIONAL MEMBERSHIPS:

American Society of Mechanical Engineers American Nuclear Society

Beta Gamma Sigma Society of Manufacturing Engineers HONORS AND AWARDS:

Frank Castelli Academic Scholarship Saint Francis University Physics Award Officer Candidate School, Distinguished Naval Graduate Temple University Executive MBA.Selection, Westinghouse Electric Corporation Beta Gamma Sigma Distinguished Scholar, Temple University NRC Team Award, December 2002, Salem Special Inspection NRC Performance Award, Spring 2003 NRC Performance Award, December 2004 NRC Performance Award, December 2005 NRC Performance Award, December 2006

Arthur D. Salomon Statement of Professional Qualifications CURRENT POSITION:

Research (Mathematical) Statistician Probabilistic Risk Analysis Branch, Division of Risk Analysis and Applications Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission, Rockville, MD EDUCATION B.S. (with distinction), Mathematics University of Michigan, April 1968 M.A., Mathematics University of Maryland, June 1971 Ph.D. Candidate University of Maryland, 1971 - 1974 Completed all requirements for Ph.D. in Mathematics, except for dissertation.

D.Sc. Candidate George Washington University, 1974- 76, 1979- 87 Part-time study in statistics and operations research; completed all requirements for D.Sc. in operations research, except for dissertation.

EXPERIENCE July 2002 - present Research (Mathematical) Statistician Responsible for review of the statistical uncertainty analysis part of the nuclear risk analysis for the Light Weight Radioisotope Heater Units (LWRHU) fueled with Pu-238 and containing other sealed sources of radionuclides used in the Mars Exploration Rover (MER) - 2003 project (with NASA and DOE).

Responsible for review of techniques used in parameter estimation for probabilistic risk assessment (PRA), and for coordination and reconciliation of comments on the PRA parameter estimation handbook. I participated in a verification and validation of SAPHIRE - a set of computer programs code used for PRA analysis, mainly for nuclear power plants.

Developed procedure for determining adverse trends in unidentified leakage rates - in support of Davis-Besse Lessons Learned Task Force.

Preparation of SOW tasks to support NRR for development of approach to construction sampling (ITAAC) for combined operating license (COL) for nuclear reactors.

Reviewed and provided comments on a strategy for hydro-geologic modeling and uncertainty analysis for nuclear facilities and sites.

Reviewed and commented on a framework for risk informing regulation of nuclear reactors using PRA methods, and reviewed a standard developed by The American Society of Mechanical Engineers (ASME) for PRA assessment for nuclear power plant applications.

Provided internal statistical consulting on uncertainty analyses. Also involved in consultation on aviation risks associated with dry cask storage at nuclear power plant sites.

May 1990 - July 2002 Electronics Engineer, Deputy Program Manager, Management and Program Analyst, General (Systems)

Engineer, and Statistician Federal Aviation Administration, Washington, DC Feb. 2000 - July 2002 Responsible for the General Aviation (GA) survey - including review of sample design, sample allocation, estimation procedures, review of survey results, and coordination of other issues related to the survey. Responsible for other GA issues, including GA forecasts, preparation of GA point papers for the FAA Administrator, and development of the GA chapters of the annual FAA forecast documents. Received cash award for the GA survey work and was granted a retention allowance by the FAA.

Provided statistical consulting to-the analysts and economists in my office and throughout the agency. Served as a member of several GA related aviation subcommittees of the Transportation Research Board (TRB) and briefed them on the status of GA at annual and semi-annual meetings.

March 1998 - Feb. 2000 Served as a general (systems) engineer in the Concept Development Branch, responsible for developing a white paper on issues involving National Airspace System (NAS) modernization and its impact on airports. Significant participant in the FAA process improvement (PI) program and in the development of the FAA integrated Capability Maturity Model (FAA-iCMM); co-authored the FAA-iCMM Appraisal Method.

Participated in CMM assessments and development of training for process improvement; involved in the development of metrics for program management. (Received awards for work related to the PI effort and the metrics development.)

July 1995 - March 1998 Served as a management and program analyst on the National Airspace System (NAS) Planning Team where I was responsible for development of (economic) service life data to be used in the preparation of needs-based resource requirements for the Long Range Resource Allocation Plan. I also began my involvement in systems engineering assessments as a member of the Systems Engineering Capability Maturity Model (SE-CMM) evaluation team.

In late 1996, the office was realigned, my branch was eliminated and I was reassigned to the NAS Concept Development Branch where I continued to serve as a management and program analyst until I was reclassified as a general (systems) engineer in March of 1998.

3-May 1992 - July 1995 Served as the deputy program manager (DPM) for terminal automation and DPM for en route, tower, and training automation - responsible for acquisition and installation of airport traffic control tower display and automation equipment, automated terminal radar display systems, and en route systems software development. Performed an active role in technical reviews, technical interchange meetings, deployment readiness reviews, and development of program budgets and schedules. As a result of a reorganization in late 1994, my office was combined into the Office of Air Traffic Systems Development (AUA). I was reassigned to the AUA Business and Financial Staff (AUA-10) where I served on that from late 1994 through July 1995. I was responsible for special projects - office business plan development as a member of the business plan team; AUA technical assistance contract (TAC) as a member of the source evaluation board and chairman of the technical evaluation team.

May 1990 - May 1992 Served as an electronics engineer on the Voice Switching and Control System (VSCS), and as-lead FAA systems engineer on VSCS -responsible for engineering requirements and system reliability and availability requirements for the technical evaluation team and for the acquisition team after the contract was awarded. Responsible for assembling (from industry and academia) the members of the VSCS Independent Fault Tolerance Assessment Team (VIFTAT) and for acting as advisor to the team.

March 1986 - May 1990 Senior Engineer Specialist Stanford Telecommunications, Inc. (STel)

Washington, DC As a senior engineer specialist (automation/reliability), served as the reliability/

maintainability/availability ,(RMA) task leader for the systems engineering support contractor to the FAA's Advanced Automation System (AAS) design competition phase (DCP) and acquisition phase (AP). Had primary responsibility for reviewing all fault tolerance and RMA activities and efforts - related to system design and performance - of the DCP contractors and AP prime system contractor. I reviewed reliability designs, reliability data collection, hardware and software reliability modeling and estimation, fault tolerance design specifications, and RMA planning and improvement. I also performed a similar role on the VSCS program just prior to joining the FAA.

Conducted an independent software reliability (probabilistic) risk assessment of the AAS software development. Provided suggestions for improving reliability modeling and estimation

- based on advances in reliability research, including incorporation of expert opinion and Bayesian techniques.

Oct. 1985 - March 1986 Senior Statistician Science Applications International Corporation (SAIC),

McLean, VA Served as the senior statistician of this SAIC group, which provided technical support to the Ground Launched Cruise Missile (GLCM) program office of the Johns Hopkins University/

Applied Physics Laboratory (JHU/APL) and to the Pershing missile program office. Participated in developing data collection methods; responsible for reviewing statistical procedures used for missile reliability and accuracy analysis. Provided recommendations for improvements to statistical analyses based on current research, and was responsible for apprising the group of advances in statistics research, operations research, and reliability.

Oct. 1983 - Dec. 1985 Systems Engineer The MITRE Corporation, McLean, VA Provided support to FAA air traffic control systems development by developing functional and performance requirements (and specifications) for Automated En Route Air Traffic Control (AERA) capabilities for the FAA AAS System Level Specification (SLS). I developed a set of performance measures for AERA capabilities and prepared a series of technical papers discussing issues involved in AERA function validation.

Served as a member of the Host Computer system (HCS) Independent Technical Assessment Group - responsible for evaluating system reliability, reliability growth, and other RMA issues.

Developed a set of reliability growth requirements for the HCS which led to the successful deployment and operational performance of the HCS.

Oct. 1978 - Oct. 1983 Mathematical Statistician Bureau of Labor Statistics (BLS), Washington, DC As a (senior) mathematical statistician with BLS, was responsible for sample size determination and sample allocation for BLS Area Wage Surveys, Industry Wage surveys, and Service Contract Act Surveys. Responsible for all statistical aspects of these surveys including weighting and non-response adjustment; was also responsible for annual development of the universe file/sampling frame used in BLS surveys.

A. Louise Lund Statement of Professional Qualifications CURRENT POSITION Branch Chief Division of License Renewal Office of Nuclear Reactor Regulation EDUCATION M.S. Materials Science and Engineering Washington State University - Tri-Cities Campus Richland, WA 5/94 B.S. Materials Science and Engineering Washington State University Pullman, WA 5/91 A.A. Nuclear Medicine Technology Prince George's Community College Largo, MD 5/79 EXPERIENCE 11/05 - present US Nuclear Regulatory Commission, Washington, DC Branch Chief, Division of License Renewal Office of Nuclear Reactor Regulation Supervises project managers responsible for coordinating the safety review of license renewal.

10/01 - 10/05 US Nuclear Regulatory Commission, Washington, DC Section Chief, Steam Generator Integrity and Chem. Eng. Section Office of Nuclear Reactor Regulation Supervised materials and chemical engineers performing technical reviews in steam generator integrity and chemical engineering topics.

1/00 - 10/01 US Nuclear Regulatory Commission, Washington, DC Materials Engineer, Office of Nuclear Reactor Regulation Performed evaluations of materials engineering-related issues to support licensee implementation of NRC regulations and requirements and to support applications for license renewal.

1/99 - 1/00 US Nuclear Regulatory Commission, Washington, DC Public Communication Advisor, Office of the Executive Director for Operations Acted as representative of the Office of the Executive Director for Operations for agency public communications and plain language issues. In this role,

developed, evaluated, coordinated, reviewed, and monitored progress on communications activities throughout the agency.

12/96 - 1/99 US Nuclear Regulatory Commission, Washington, DC Materials Engineer, Office of Nuclear Regulatory Research Responsible for planning, directing, and coordinating external research efforts associated with materials behavior, irradiation effects, fracture mechanics, and structural integrity of a nuclear reactor primary system. Developed standards and regulations associated with the safety-related materials aspects of reactor facilities.

7/92 - 11/96 Pacific Northwest National Laboratory, Richland, WA Research Scientist, Structural Materials Research Section (1/94 - 11/96)

Research Assistant, Structural Materials Research Section (7/92 - 1/94)

Marketed, planned, organized, directed, and coordinated multi-disciplinary research projects to characterize materials performance using corrosion and metallurgical engineering techniques. Managed projects with funding levels up to $200K.

Directed the activities of technicians, technical specialists, and students working on research projects.

2/80 - 7/92 Various Commercial Nuclear Power Plants Health Physics Contractor/Consultant Provided health physics support, wrote procedures, and trained utility and contract personnel during maintenance outages and reactor start-up operations in sixteen commercial nuclear power plants. Supervised utility and contract personnel during some contract assignments.

'79 -'80 Arlington Hospital, Arlington, VA Registered Nuclear Medicine Technologist Performed diagnostic nuclear medicine tests, and administered iodine therapy as directed.

PUBLICATIONS Lund, A.L. et al., "Welding as a Repair Option for BWR In-Vessel Components," 9th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, August 1 - 5, 1999.

Carpenter, C.E., Jr., and A.L. Lund, "BWR Internals Cracking Issues," Paper #438, CORROSION/99 Conference Paper, San Antonio, TX, March, 1999.

Lund, A.L., et al., "The Effect of the Displacement Control Routine on the Elongation to Failure and Failure Morphologies in Superplastic AA-5083," Automotive Alloys, ASM International, Dr.

Subodh Das, ed., February, 1997.

Lund, A.L., "Feasibility of Underwater Welding in Highly Irradiated In-Vessel Components of Boiling-Water Reactors," NUREG-1616, November 1997.

Lund, A.L., et al., "Corrosion Assessment of High-Strength Materials Used in a Void Fraction Instrument for Hanford Waste Tanks." Paper #96113. CORROSION/96 Conference Paper, Denver, CO, March 24 - 29, 1996.

Lund, A.L. and M.J. Danielson, "Sludge Washing Materials Study Update: The Materials Performance of Carbon Steel in Very Dilute Waste Environments," Paper #96115, CORROSION/96 Conference Paper, Denver, Colorado, March 24 - 29, 1996.

Lund, A.L. and M.J. Danielson, "Pretreatment Applied Engineering, Corrosion Assessment for Tank Materials: 1995 Final Report," PNNL-11219, June 1996.

Johnson, A.B. Jr., A.L. Lund, and S.P. Pednekar, "Estimates of Durability of TMI-2 Core Debris Canisters and Cask Liners," PNL-9457, April 1994.

Kamal Manoly Statement of Professional Qualifications CURRENT POSITION Chief, Mechanical and Civil Engineering Branch (EMCB)

Division of Engineering Office of Nuclear Reactor Regulation, NRC EDUCATION B.S. Civil Engineering, Structural Major, Ain Shams University, Cairo, Egypt, 1968 M.S. Civil Engineering, Structural Major, Villanova University, PA, 1972 M.S. Applied Solid Mechanics, Drexel University, PA, 1978

SUMMARY

Over thirty eight (38) years of experience in structural analysis, design, and engineering mechanics. Three (3) years of experience in the structural design of industrial and commercial facilities, and highway bridges. Eleven (11) years of experience in the analysis and design of nuclear power plant structures, containments, pressure boundary components, and seismic qualification of mechanical and electrical equipment. Twenty four (24) years of experience in nuclear regulatory inspection, review and evaluation, and development of standards for nuclear mechanical components.

EXPERIENCE US Nuclear Regulatory Commission, August 1983 - Present

  • Conducted routine and specialized inspections of nuclear power plants under construction and nuclear power plants in operation in Region-1.

" Participated in numerous team inspections prior to granting of operating license to several nuclear power plants in Region-i.

" Conducted several special inspections, and participated in extensive design audits for resolution of allegations involving Seabrook, Millstone-3, and Diablo Canyon nuclear plants prior to granting of operating licenses.

" Selected and performed the function of a technical assistant to the Director of the Division of Engineering in NRR for four years.

" Selected as a Section Chief in the Mechanical Branch of the Division of Engineering in NRR, and later as a Branch Chief of the Mechanical and Civil Engineering branch (EMCB) in NRR.

" Supervised the review of license renewal applications in the structural and metal fatigue areas, and the review of power uprate amendment requests, and three early site permits.

  • Developed several Generic Communications and guidance documents related to qualifications for nuclear power plant equipment, and structural adequacy of mechanical components.

" Provided technical support to regional offices in resolving a variety of structural and mechanical findings.

  • Supported the update of the Standard Review Plan and Regulatory Guides within the scope of responsibility of EMCB.

" Represented and continue to function as NRC representative on various American Society of Mechanical Engineers (ASME),Section III, Working Groups: Subgroup on Design, Subcommittee on Nuclear Power, and Main Committee on Qualification of Active Mechanical Equipment in Nuclear Power Plants.

Target Technology Ltd., Malvern. PA, October 1979 - August 1983 Joined Target in the capacity of Consulting Structural Engineer. Named Manager of Structural Engineering Department in May, 1980.

  • Appointed Project Engineer for the following activities:
  • Seismic interaction review of Dresden 2 Nuclear Power Station in conjunction with the NRC's Systematic Evaluation Program (SEP) for Commonwealth Edison Company.

" High Energy Line Break Evaluation inside Containment for Dresden Station.

  • Consulting Engineering Services Contract with Port Authority of the State of N.Y. for modification inside reactor for James A. Fitzpatrick Nuclear Power Plant. Modifications included piping, conduits, tubing and related supports.
  • Appointed head of the engineering staff responsible for the development of "Automated Design of Pipe Supports," a library of the most commonly used configurations of pipe supports, for use by design engineers utilizing a desk top personal computer.
  • Held Supervisory responsibilities for the following activities:
  • Seismic qualification of the Drive Train assemblies for Seabrook Station Units 1 & 2
  • Evaluation of component cooling water heat exchangers for Florida Power & Light Turkey Point Plant, Units 3 & 4.

" Review of design verification and stability analysis of fiberglass fanstacks for ceramic cooling towers.

" Review of pipe support re-evaluation on the James A Fitzpatrick NPP in accordance with NRC, IE Bulletins 79-14 and 79-02.

  • Participated in planning and instruction of lecture series on Pipe Support Design for the Philadelphia Electric Company.

" Prepared bids and related cost estimate, schedule development, and projection of manpower needs for new business.

Stone & Webster Engineering Corporation, Cherry Hill, NJ, October 1973 - October 1979 Joined as Structural Mechanics Engineer on Gulf States (BWR) nuclear power plant design project in Louisiana. Later named as task engineer with additional supervisory function.

Responsibilities included participation in the following:

" Analysis and design of the turbine support pedestal.

" Analysis and design of structures in the reactor building: mat foundation, pressure vessel support, containment vessel stiffening system, and shield structure dome.

" Seismic analysis of reactor, fuel, and turbine structures.

  • Establishment of procedures and writing of specifications for the conduction of the structural acceptance test for the reactor's drywell concrete structure and the steel containment vessel.

Supervisory responsibilities included:

  • Review of final analysis and design calculations prior to audit.
  • Supervision of new engineering graduates in the Career Development Program.

United Engineer and Constructors Inc., Philadelphia, PA, November 1972 - October 1973 Joined as a Structural Design Engineer in the Power Division on the Washington Public Power Supply System Nuclear Power Plant design project in Washington state. Responsibilities included:

" Layout, analysis and design of the General Service Building.

" Static and seismic analysis on the intake structure.

  • Feasibility study of the excavation required to prepare the plant site for construction.

John G. Reutter Associates, Camden, NJ, August 1970 - November 1972 Appointed as a Structural engineer on several projects. Responsibilities included:

  • Structural analysis and design of several highway bridges in New Jersey.
  • Structural design and verification of various sewage treatment plants in southern New Jersey.
  • Structural design of pumping stations for sewage treatment plants.

Urban Engineers Inc., Philadelphia, PA. October 1969 - August 1970 Appointed as Structural Design Engineer. Responsibilities included the following projects:

" Structural design, quantity calculation, and cost estimate of expansion and modernization of the Philadelphia International Airport.

" Design of a library for Cheyney State College in Pennsylvania.

" Verification of design calculations for Temple University hospital buildings in Philadelphia.

Contracting Engineering Office "ARCTIC", Cairo, Egypt, December 1968 - September 1969 After graduation, was hired in an architectural contracting firm with responsibility for structural design and supervision of construction of public buildings.

REGISTRATION Former Professional Engineer in the State of Pennsylvania.

PROFESSIONAL SOCIETIES During employment at the NRC, served on the American Society of Mechanical Engineers (ASME),Section III, Working Groups on Piping Design and Vessels. Currently, represent the NRC on ASME,Section III, Subgroup Design, and Subcommittee on Nuclear Power. Also represent the NRC on ASME Main Committee for Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.

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