ML042260299
| ML042260299 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/14/2004 |
| From: | Dunn B Framatome Technologies |
| To: | Office of Nuclear Reactor Regulation |
| Byrdsong A T | |
| References | |
| 50-413-0LA, 50-414-OLA, ASLBP 03-815-03-OLA, Catawba-Applicant-49, RAS 8311 | |
| Download: ML042260299 (3) | |
Text
INUCLEAh RELIULA1ORY COMjmwSSIl;q a45 AS 3 /1/
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In the matter of
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Intervenor-Cnntrg Off',r Cntractor -
IDENTIFIED
/1/0lq RECEIVED_____(___
REJECTED DATE _
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331 ERT M. DUNN AREVA Old Forest Road hburg, VA 24501 DOCKETED USNRC August 9, 2004 (11:45AM)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF view-Porter_0Xvvd xh-N yic A_
EDUCATION:
EXPERIENCE:
3/84-Present BS in Physics, Washington State University, 1968 MS in Physics, Lynchburg College, 1973 AREVA Framatome ANP Inc. (formerly Framatome Nuclear Technologies Inc., Nuclear Power Division of the Babcock & Wilcox Company), Lynchburg, Virginia Advisory Engineer AREVA representative to high burnup industry forums responsible for providing recommendations on licensing criteria to NRC. Lead on AREVA consultation with NRC on irradiated fuel LOCA testing at Argonne National Laboratory.
Member of U.S. NRC High Burnup Fuel Design Basis Accident Technical Evaluation PIRT (Phenomena Identification and Ranking Table) Panel.
Technical lead for the development of LOCA and Safety Analysis techniques for the licensing of new fuel cladding materials.
Technical lead for the development of evaluation techniques to determine the outcome of inherent boron dilution events.
Technical co-lead for the evaluation of best estimate LOCA licensing techniques.
Project lead for development of Loss-of-Coolant-Accident analysis capability for Westinghouse and Combustion Engineering plants.
Senior Product Manager Project Manager for Pressurized Thermal Shock (PTS) B&W Owners Group Task Force. Lead development of a probabilistic risk assessment for PTS in B&W plants.
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Bert M. Dunn 1975-1980 Unit Manager. Emergency Core Cooling System Analysis Responsible for all ECCS evaluations of the performance of B&W-designed nuclear power plants.
1970-1975 Engineer/Supervisory Engineer Licensing of B&W's ECCS evaluation models and development of techniques for evaluating reactor building subcompartment pressure forces.
1968-1970 Engineer - Douglas United Nuclear Corporation. Richland, Washington Reactor physics, fuel engineering, operations.
PUBLICATIONS:
Major contributor or the principal author of:
- a.
BAW-10034, "Multinode Analysis of B&W's 2568 MWt Nuclear Plants During a Loss-of-Coolant Accident," October 1971.
- b.
BAW-10045, "Multinode Analysis of B&W's 205-Fuel Assembly Nuclear Plants During Loss-of-Coolant Accident,"
May 1972.
- c.
BAW-10052, "Multinode Analysis of Small Breaks for B&W's 2568 MWt Nuclear Plants," September 1972.
- d.
BAW-10064, "Multinode Analysis of Core Flooding Line Break for B&W's 2568 MWt Internals Vent Valve Plants," April 1973.
- e.
BAW-10091, "B&W's ECCS Evaluation Model Report With Specific Application to 177-FA Class Plants With Lowered-Loop Arrangement," August 1974.
- f.
BAW-10091, Supplement 1, "Supplementary and Supporting Documentation for B&W's ECCS Evaluation Model Report With Specific Application to 177-FA Class Plants With Lowered-Loop Arrangement," December 1974.
- g.
BAW-10102, "ECCS Evaluation of B&W's 205-FA NSS," June 1975.
- h.
BAW-10104, "B&W's ECCS Evaluation Model," May 1975.
2
Bert M. Dunn
- i.
BAW-10106, "- QUENCH - Digital Program for Analysis of Core Thermal Transients During Loss-of-Coolant Accident,"
May 1975.
3