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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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NUCLEAR REGULATORY COMMISSION VT% . -
5 Docket No. 0 1 Official Exh. No. q42IJ5 8'g3 A In the mntter of P WV raCobhuk staff v__ {d IDENTIFIED ...7/L0 7L /Y Applicant RECEIVED Attachment 2 Intervener *. REJECTED DOCKETED Cont'g Off'r~ USNRC Contractor DATE ROBERT C.HARVEY August 9, 2004 (11:45AM)
Other _ ___ Wltness Duke Power OFFICE OF SECRETARY Re 52 South Church St RULEMAKINGS AND Charlotte, NC 28202 ADJUDICATIONS STAFF QUALIFICATIONS:
25 years of Thermal Hydraulic and Safety Analysis experience supporting the reload and licensing of pressurized water reactors. Mr. Harvey has performed numerous safety analysis calculations using the RELAP4, RELAP5, RETRAN, TOODEE-2, CONTEMPT-LT, and MAAP computer codes.
EDUCATION:
Nuclear Engineering Graduate Studies, University of Lowell (1980-1982)
BS, Nuclear Engineering, University of Lowell, 1979 Supervisory Training, Yankee Atomic Electric Company, 1994 MAAP Code Utilization and Phenomena seminar, Fauske & Associates Two-Phase Gas-Liquid Flow Seminar, University of Houston Nuclear Power Reactor Safety Seminar, Massachusetts Institute of Technology (MIT)
Simulator Training, Combustion Engineering (CE)
Two-Phase Flow and Heat Transfer, Rensselaer Polytechnic Institute EXPERIENCE:
Senior Engineer - Duke Power Company 2/99 - present Lead Engineer responsible for the LOCA analysis supporting the Oconee, McGuire, and Catawba nuclear plants. Responsibilities include providing interface and oversight of the vendor analyses. In addition, performs LOCA mass and energy release calculation used as input to the containment analysis and performs UFSAR Chapter 15 non-LOCA safety analysis. Specific accomplishments include supporting the Oconee reanalysis to support steam generator replacement and the transition to best-estimate LOCA analysis methods for the McGuire and Catawba units. Serves as a member of the Emergency Operations Facility (EOF) in the position of Accident Assessment Manager.
Provided an independent assessment of the Texas Utilities LOCA analysis supporting the transition to Westinghouse fuel.
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Robert C. Harvey Engineer - Duke Engineering & Services - (12/97 - 1/99); Senior Nuclear Engineer -
Yankee Atomic Electric Company (5/91 - 11/97)
Lead Engineer for pressurized water reactor (PWR) LOCA analyses supporting licensing for the Yankee Rowe, Maine Yankee and Seabrook Nuclear Power Stations. Areas of involvement included LOCA and containment analyses and severe accident analyses related to Individual Plant Evaluations (IPEs). Specific accomplishments included supporting the Maine Yankee small break loss of coolant accident (SBLOCA) analysis to justify a return to 2440 MWth operation, and providing oversight of Siemens Power Corporation SBLOCA re-analysis. Served as a response team member to Maine Yankee 1996 Independent Safety Assessment.
In addition, supported General Electric (GE) in severe accident analysis for simplified boiling water reactor (SBWR) certification and provided consulting to the Siemens fuel user group in the area of LOCA analysis.
Provided support to Northeast Utilities on severe accident management guidelines (SAMGs) for Millstone Units 2 & 3 and the Seabrook Nuclear Power Station and performed a technical review of ABB/CE reload analysis of St. Lucie Unit 2 for FP&L.
Senior Engineer - Yankee Atomic Electric Company 5/88 - 5/91 Lead Engineer for Yankee Rowe and Seabrook LOCA analysis related activities and for all severe accident analysis activities. Duties involved reload licensing analysis for the Yankee Rowe plant and vendor oversight of Seabrook LOCA analysis activities.
Supported the plant specific model development and certification of the Yankee Rowe plant simulator. Participated in the Yankee Rowe plant life extension (PLEX) effort providing support in severe accident evaluations and pressurized thermal shock (PTS) analysis. Also, provided training to Texas Utilities personnel in LOCA analysis method applications.
Nuclear Engineer - Yankee Atomic Electric Company 5/85 - 5/88 Lead Engineer for Yankee Rowe LOCA analysis related activities. Activities included large break loss of coolant accident (LBLOCA) model development and applications related to reload licensing, steam generator tube rupture (SGTR) analysis and plant request responses. Participated in the development of Yankee Rowe, plant specific emergency operating procedures (EOPs) based on the generic Westinghouse Owners Group (WOG) emergency response guidelines (ERGs). Performed a plant specific analysis to support deviations from the generic WOG guidelines. Also, provided training to Korean Power (KEPCO) engineers in LOCA analysis methods.
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Robert C. Harvey Engineer- Yankee Atomic Electric Company 6/79 - 5/85 Performed LBLOCA analyses in support of reloads for the Yankee Rowe and Maine Yankee plants. Contributed to model enhancements of the LBLOCA methods used for Yankee Rowe. Participated in developing and assessing the RELAP5YA computer code used for PWR SBLOCA analysis.
PROFESSIONAL AFFILIATIONS/CERTIFMCATIONS:
American Nuclear Society (ANS), Member The Research Society of Sigma Xi, Associate Member Registered Professional Engineer North Carolina (Registration # 027387)
South Carolina (Registration # 22237)
SELECTED PUBLICATIONS:
- 1. Maine Yankee Steam Generator Tube Sleeving Thermal-Hydraulics and Safety Analysis Impacts, co-authors K. R. Rousseau, S. Palmer, P. A. Bergeron, presented at the American Power Conference, Chicago, Ill., 1995.
- 2. Maine Yankee Cycle 15 Core Performance Analysis, YAEC-1907, co-authors, January 1995.
- 3. Yankee Rowe Pressurized Thermal Shock, Thermal-Hydraulic Analysis, International Heat Transfer Conference, co-authors P. A. Bergeron, N. Fujita, August 1993.
- 4. Maine Yankee Level 1H PRA Results, ASME/JSME International Conference on Nuclear Engineering, co-author K. E. St. John, March 1993.
- 5. Thermal Hydraulics Analysis of the Yankee Plant Due to a Stuck Open PORV Using RELAP5/MOD3 Computer Code, RELAP5/TRAC-B International Users Seminar, co-authors W. S. Yeung, R. K. Sundaram, November 1991.
- 6. Yankee Plant Small Break LOCA Analysis, YAEC-1732, co-authors S. Mihaiu-Westerlind, R. K. Sundaram, July 1990.
- 7. Yankee Nuclear Power Station Core 21 Performance Analysis, YAEC-1731, co-authors, July 1990.
- 8. Yankee Nuclear Power Station Severe Accident Closure Submittal, YAEC-1711, co-authors, December 1989.
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II . I Robert C. Harvey
- 9. Plant-Specific Analysis to Support the Yankee Emergency Operating Procedures, YAEC-1663, co-authors, April 1989.
- 10. Seabrook Station Risk and Plant Response for Low Power Operating Conditions, YAEC-1623, co-authors, March 1988.
- 11. RELAP5YA Simulation of LOFT Small Break Experiments L3-6 and L5-1, Transactions American Nuclear Society, Volume 55, co-authors, L. Schor, November 1987.
- 12. Estimate of Peak Clad Temperature and Its Uncertainty in a Large Break LOCA at Yankee Nuclear Power Station, YAEC-1431P, co-authors, R. K. Sundaram, K. E. St.
John, May 1984.
- 13. RELAP5YA - A Computer Program for Light Water Reactor System Thermal-Hydraulic Analysis, YAEC-1300P, co-authors, R. T. Fernandez, R. K. Sundaram, J.
Ghaus, A. Husain, J. N. Loomis, L. Schor, R. Habert, October 1982.
- 14. RELAP4 and RELAP5 Calculation of LOFT L3-5 and L3-6 Experiments: Comparison to Data, ANS Specialists Meeting on Small Break Loss-of-Coolant Accident Analyses in LWRs, co-authors, L. Schor, J. N. Loomis, A. Husain, August 1981.
- 15. RELAP4 Analysis of CREARE Flashing Transients with Reverse Core Steam Flow, Transactions American Nuclear Society, Volume 38, co-authors G. J. Brown, A.
Husain, August 1981.
- 16. Applications of a Lower Plenum Phase Separation Model to Yankee Rowe Large Break LOCA Analysis, YAEC-1231, Revision 1, co-authors, March 1981.
- 17. Maine Yankee Cycle 5 Core Performance Analysis, YAEC-1202, co-authors, December 1979.
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