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Category:Legal-Exhibit
MONTHYEARIR 05000413/20083012009-02-0505 February 2009
Official Exhibit - CCS-118-00-BD01 - Catawba Nuclear Station NRC Operator License Examination Report 05000413-08-301 and 05000414-08-301
ML0513600792005-02-17017 February 2005
Security Exhibit List for Hearing Held from January 11 to January 14, 2005
ML0506702592005-01-13013 January 2005
Catawba Hearing - Staff Exhibit (SEC-28), Attachment 1. Resumes of Sherri L. Cross, Albert G. Garrett, Michael R. Burrell, R. John Vanden Berghe, John Brian Mckirgan, and William Troskoski
ML0506702552005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 8 (SEC-13), IAEA Safeguards Glossary 2001 Edition. International Nuclear Verification Series No.3
ML0506702152005-01-13013 January 2005
Catawba Hearing - Staff Exhibit 8 (SEC-24), the Physical Protection of Nuclear Material and Nuclear Facilities
ML0506701562005-01-13013 January 2005
Catawba Hearing - Staff Exhibit 7 (SEC-23), Technical Reports Series No.415, Status and Advances in MOX Fuel Technology
ML0506701442005-01-13013 January 2005
Catawba Hearing - Intervener Exhibit 14 (SEC-19), Doe'S Involvement in Negotiations on the Question of Whether to Revise the Convention on Physical Protection of Nuclear Material
ML0506701062005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 5 (SEC-10), NUREG/CR-1378, Rev 1, Hardening Existing Strategic Special Nuclear Material Storage Facilities
ML0506701042005-01-13013 January 2005
Catawba Hearing - Intervenor Exhibit 1 (SEC-9), Curriculum Vitae of Edwin Stuart Lyman
ML0506700932005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 4 (SEC-4), Resume of Howard B. Williams
ML0506700862005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 1 (SEC-1), Steven P. Nesbit Statement of Professional Qualifications - Rec'D 01/11/05
ML0506700892005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 2 (SEC-2), Resume of Glenn A. (Skip) Copp, III
ML0506700902005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 3 (SEC-3), Resume of William Thomas Byers, III
ML0506700982005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 5 (SEC-5), Resume of Rita A. Edwards
ML0506701012005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 14 (SEC-7), Diagram of FS-65 Transportation Package, Cross-Section
ML0506701132005-01-11011 January 2005
Catawba Hearing - Applicant Exhibit 15 (SEC-8), Duke Energy Corp. Administrative Change to Facility Operating Licenses in Conjunction with the Commission Order EA-03-088 Re Revised Design Basis Threat and Revisions to Safeguards.
ML0506702622005-01-0909 January 2005
Catawba Hearing - Intervenor Exhibit 22 (SEC-A), the Big Gun, Broadcast on CBS Tv Show 60 Minutes
ML0503801632004-12-31031 December 2004
R. Nevin Staff Exhibit 6, Nirs/Pc EC-7: Duke Power, About Us Nuclear Power Plants, 2004, Available at Http://Www,Dukepower.Com/Aboutus/Plants/Nuclear
ML0422603132004-07-16016 July 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 52, Y. Yan, Et Al., LOCA Results for Advanced-Alloy and High-Burnup Zircaloy Cladding - Rec'D 07/15/04
ML0422603652004-07-15015 July 2004
Catawba Hearing 07/15/04 - Applicant Exhibit D, E. H. Karb, Et Al., Results of the FR2 In-Pile Tests on LWR Fuel Rod Behavior - Identified 07/15/04
ML0422603062004-07-15015 July 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 51, J. Papin, Et Al., Synthesis of CABRI-RIA Tests Interpretation - Rec'D 07/15/04
ML0422600822004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 19 - Figure 14, Figure M5 Rupture Strain Versus Rupture Temperature Slow Ramp Rate - Rec'D 07/14/04
ML0422602282004-07-14014 July 2004
Catawba Hearing 07/14/04 - Staff Exhibit 3 (Official Exhibit #40), Excerpt from Y. Yan, Et Al. Slide Presentation of LOCA Test Results for High-Burnup BWR Fuel and Cladding - Rec'D 07/14/04
ML0422602212004-07-14014 July 2004
Catawba Hearing 07/14/04 - Staff Exhibit (Official Exhibit #37), Professional Qualifications Statements of Undine Shoop, Ralph R. Landry, and Ralph O. Meyer - Rec'D 07/14/04
ML0422600432004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 10 - Figure 5, Thermal Conductivity Comparison for MOX and Leu Fuel (Fuel Porosity of 0.0479) (Figure Q21-1) - Rec'D 07/14/04
ML0422602122004-07-14014 July 2004
Catawba Hearing 07/14/04 - Intervenor Exhibit H (Official Exhibit #32), NUREG/CR-6744, Phenomenon Identification and Ranking Tables (Pirts) for Loss-of-Coolant Accidents in Pressurized and Boiling Water Reactors... - Rec'D 07/14/04
ML0422600742004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 16 - Figure 11, FR2 Test E4 for High Exposure Fuel (Relocation) - Rec'D 07/14/04
ML0422600182004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 08 - Figure 3, Mox/Leu Decay Heat Ratio - Rec'D 07/14/04
ML0422601132004-07-14014 July 2004
Catawba Hearing 07/14/04 - Intervenor Exhibit a (Official Exhibit #25), Edwin Stuart Lyman Curriculum Vitae - Rec'D 07/14/04
ML0422601082004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 18 - Figure 13, Figure M5 Rupture Temperature Correlation - Rec'D 07/14/04
ML0422601052004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 24 - Figure 19, Accumulated Cycle Irradiation in Effective Full Power Days - Rec'D 07/14/04
ML0422600952004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 23 - Figure 18, Fuel Exposure, Gwd/T - Rec'D 07/14/04
ML0422600912004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 22 - Figure 17, Micrograph of Irradiated MOX Pellet (Rg) - Rec'D 07/14/04
ML0422600862004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 21 - Figure 16, Micrograph of Irradiated Leu Fuel Pellet with Transverse Crack - Rec'D 07/14/04
ML0422600852004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 20 - Figure 15, Micrograph of Irradiated Leu Pellet with Typical Cracking - Rec'D 07/14/04
ML0422600312004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 14 - Figure 9, Previously Irradiated Rod 12, 74% Total Circumferential Elongation, 1066 K Estimated Burst Temperature - Rec'D 07/14/04
ML0422600762004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 17 - Figure 12, MOX Fuel and Cladding Temperature During LOCA Compared to Severe Accident Fuel Melt Temperatures - Rec'D 07/14/04
ML0422600172004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 07 - Figure 2 - Rec'D 07/14/04
ML0422602952004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 47, Professional Qualifications Statement of Steven P. Nesbit - Rec'D 07/14/04
ML0422602982004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 48, Professional Qualifications Statement of Robert C. Harvey - Rec'D 07/14/04
ML0422600302004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 13 - Figure 8 - Rec'D 07/14/04
ML0422600732004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 15 - Figure 10, FR2 Test B3.1 for Low Exposure Fuel (No Relocation) - Rec'D 07/14/04
ML0422600262004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 12 - Figure 7, Pin Power Peaking Factor, Fq, Cycle Exposure, EFPD - Rec'D 07/14/04
ML0422602992004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 49, Professional Qualifications Statement of Bert M. Dunn - Rec'D 07/14/04
ML0422603052004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 50, Professional Qualifications Statement of J. Kevin Mccoy - Rec'D 07/14/04
ML0422600222004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 11 - Figure 6, Pellet Radial Power Profiles 0.5 Gwd/T (Figure Q7-1) - Rec'D 07/14/04
ML0422600202004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 09 - Figure 4, MOX and Leu Fuel Pin Temperature Profile Comparison at Loss of Coolant Accident Initiation - Rec'D 07/14/04
ML0422600142004-07-14014 July 2004
Catawba Hearing 07/14/04 - Applicant Exhibit 06 - Figure 1, Catawba MOX LOCA Temperatures - Rec'D 07/14/04
ML0422602742004-06-14014 June 2004
Catawba Hearing 07/14/04 - Staff Exhibit a (Official Exhibit #43), E-mail from Wolfgang Wiesenack to Miroslav Hrehor Re Statement in One of Segfsm Reports - Rec'D 07/14/04
ML0422603172004-06-0707 June 2004
Catawba Hearing 07/15/04 - Intervenor Exhibit 53, E-mail from Robert C. Harvey to Steven P. Nesbit Re Oecd/Nea/Csni Special Experts Topical Meeting on LOCA Fuel Safety Criteria, Cadarache France, March 22-23, 2001 - Rec'D 07/15/04
2009-02-05
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'RAS 3 DOCKETED Attachment 4 Dr. J. Kevin McCoy August 9,2004 (11:45AM) Advisory Engineer- Materials OFFICE OF SECRETARY FramatomeANP Inc RULEMAKINGS AND '
ADJUDICATIONS STAFF General Background Dr. McCoy, a veteran scientistlengineer, has more than 20 years' experience, largely in the nuclear industry. He has proposed, planned, and executed research projects for the Nuclear Regulatory Commission (NRC), the Air Force Office of Scientific Research (AFOSR), the National Science Foundation (NSF), and the Electric Power Research Institute (EPRI). Dr.
McCoy's research included developing models for waste glass degradation, identifying a new mechanism for densification of ceramics, vectorizing computer codes to run 500 times faster, and studying boundaries between quasi-periodicity and chaos as it applies to hydrogen embrittlement. In his research, Dr. McCoy developed methods for calculating the positions of atoms at a crack tip. He even found a method for calculating the energy barrier that must be surmounted to break one atomic bond.
Dr. McCoy worked on the Yucca Mountain Project (YMP) for nearly eight years, providing leadership and technical expertise on materials selection and nuclear waste behavior. He coordinated the efforts of Frarnatome ANP, Inc. and Lawrence Livernore National Laboratory to identify material properties and make material selection for the waste packages slated for use in the proposed geologic repository. Also, Dr. McCoy led the revision of a comprehensive report on nuclear waste behavior. This report summarizes $25 million worth of research and is one of nine major documents used to support the site recommendation for the nation's first high-level radioactive waste repository.
His recent work has focused on the behavior of commercial nuclear fuel. In the past three years he has written or revised topical reports on dry fuel storage and the performance of a mixed oxide fuel assembly. He has also written several reports on poolside postirradiation examinations of irradiated fuel.
Education Ph.D., Materials Engineering, Purdue University M.S., Metallurgical Engineering, Purdue University
- B.S. (with Highest Distinction), Metallurgical Engineering, Purdue Unikversity Oualifications/Certifications I
- Good conversational and written French 'i
- Listed in Who's Who in Science and Engineering l ,
- Member, American Nuclear Society Publications !
Civilian Radioactive Waste Management System Man genieni & Operating Contractor, Waste Forn Degradation Process Model R~por, TDR-WIS-MD-000001 REV 00 ICN 01, July 2000. 1 klnplat c ford-6 PS
NUCLEAR REGULATORY COMMISSInN gNQ-qj1q4 - OL Octicml Exh. No. l 5o DO" fet in to* P't of etkd:M CA+Z" 1,4 X _ IDENTIFtED 7I1 7 104 RMcIVED_____
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Dr. J. Kevin McCoy Representative of more than 30 peer-reviewed journal articles authored or co-authored are:
D. Stahl, J. K. McCoy, and R. D. McCright, "Impact of Thermal Loading on Waste Package Material Performance", in Scientific Basis for Nuclear Waste Management XVIII, 671-678, ed. T. Murakami and R. C. Ewing, Materials Research Society, Pittsburgh (1995).
- J. K. McCoy, D. Stahl, and T. A. Buscheck, "A Corrosion Model for Waste Package Corrosion-Allowance Materials", in Proceedings of the Sixth Annual International Conference on High Level Radioactive Waste Management, 565-567, American Nuclear Society, La Grange Park, Illinois, and American Society of Civil Engineers, New York (1995).
- J. K. McCoy, "Fuel and Cladding Oxidation Under Expected Repository Conditions", in Proceedings of the Seventh Annual International Conference on High Level Radioactive Waste Management, 396-397, American Nuclear Society, La Grange Park, Illinois, and American Society of Civil Engineers, New York (1996).
Publications - continued
- J. K. McCoy, "Mechanical Failure of Commercial Spent Nuclear Fuel Cladding",
in Proceedings of the Sixth International Conference on Nuclear Engineering, 632-633, American Society of Mechanical Engineers, New York (1998).
- J. A. Blink, T. W. Doering, J. K. McCoy, R. W. Andrews, J. H. Lee, D.
Sevougian, V. Vallikat, D. G. McKenzie, and J. N. Bailey, "Factors Affecting Performance of Engineered Barriers", in Proceedings of the Eighth Annual International Conference on High-Level Radioactive Waste Management, 290-292, American Nuclear Society, La Grange Park, Illinois (1998).
Applicable Work Experience Advisory Engineer HI, Framatome ANP, 1993 - Present
- Revised topical report on performance of a mixed oxide fuel assembly. Report compares materials and performance of mixed oxide and low-enriched uranium fuels
- Wrote topical report on behavior of spent nuclear fuel in dry storage. Provided justification for increasing the allowable burnup limit
- Prepared six reports on poolside postirradiation examinations of nuclear fuel assemblies
- Predicted behavior of high-level radioactive wastes and support selection of waste container material 2
Dr. J. Kevin McCoy
- Led revision of a comprehensive report on nuclear waste behavior. Report summarizes $25 million worth of research and is one of nine major documents that supported site recommendation for the nation's first high-level nuclear waste repository
- Critically reviewed models for creep rupture of spent fuel cladding. Determined that previous models did not adequately account for cladding texture. Showed that inclusion of the effects of texture increases predicted creep life by a factor of six
- Developed novel mathematical approach for describing degradation of spent nuclear fuel. The new approach is based on a deep insight into the similarities in the degradation behavior of fuel rods that start to degrade at different times.
Lengthy performance calculations are now performed more than ten times faster
- Developed computer model to simulate bending and breaking of fuel rods during earthquakes. Proved that earthquakes strong enough to break fuel rods occur only once in a million years and would have very little effect on repository performance.
Principal Research Scientist, Battelle, Metals and Ceramics Department, Columbus, Ohio (1981-1992)
- Proposed, planned, and executed research projects. Analyzed physical processes in materials, mostly with C code. Provided own research support. Served as system administrator for departmental UNIX computer system with twenty users
- Developed methods for calculating the positions of atoms at a crack tip. Found method to calculate the energy barrier that must be surmounted to break one atomic bond. Knowing the height of the barrier is critical for calculating crack growth rates. This breakthrough came after several years of unsuccessful efforts by other scientists
- Developed technique for instrumenting hot isostatic pressing. Instrumentation provides a continuous record of material behavior and increases the amount of data obtained from costly experiments by three to five times
- Managed personal computer resources for department with fifty users. Planned hardware acquisitions and allocated resources.
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