ML12089A626
| ML12089A626 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/29/2012 |
| From: | Kimberly Green Division of License Renewal |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| Shared Package | |
| ML12089617 | List: |
| References | |
| RAS 22134, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML12089A626 (2) | |
Text
Statement of Professional Qualifications Kimberly J. Green, Senior Project Manager Branch 2, Division of License Renewal Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission Ms. Green is a nuclear engineer with over twenty years of experience in safety analysis, design modifications, license renewal, and radiological controls. Her expertise includes regulatory analysis and the evaluation of licensing documentation, particularly in the area of license renewal reviews. She has been a contractor to the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Her experience in private industry has included performing safety analyses in support of steam generator replacements at commercial power plants. Ms.
Green is currently a senior mechanical engineer responsible for the technical review of aging management programs and aging management review results for auxiliary systems for license renewal applications. In addition, she is one of the senior project managers for the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application.
EDUCATION B.S. Engineering, University of Maryland, College Park, MD, December 1989 Major: Nuclear Engineering Minor: Mechanical Engineering EXPERIENCE From 2006-present, at the U.S. NRC, Ms. Green has been a senior mechanical engineer responsible for the NRC Staffs technical review of aging management programs and aging management review results for auxiliary and steam and power conversion systems for license renewal applications. She is also a senior project manager for the NRC Staffs environmental review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) license renewal application (LRA). Until April 2011, Ms. Green was the senior project manager for the NRC Staffs safety review for the IP2 and IP3 LRA the, responsible for the development and implementation of the project schedule and the safety evaluation report. She has been responsible for the issuance of requests for additional information, and the final safety evaluation report. She was also a member of the audit teams that evaluated the applicants scoping and screening methodology, aging management reviews and aging management programs. Ms. Green also served as the NRC Staffs senior project manager for the safety review of the Diablo Canyon Nuclear Power Plant license renewal application and had the same responsibilities as for the Indian Point license renewal application. As a mechanical engineer, Ms. Green was a member of the scoping and screening methodology audit team for the Wolf Creek, Susquehanna and Shearon Harris license renewal applications. As an audit team member, she evaluated the scoping and screening methodology for the plant-specific license renewal applications to determine if the applicants methodology meets the intent of 10 CFR Part 54.
From 2000 to 2006, at Information Systems Laboratories, Inc., Ms. Green was a contractor to the U.S. NRC, involved in the NRC Staffs safety review of numerous license renewal applications. In particular, she performed engineering evaluations of the main steam, feedwater, auxiliary feedwater, instrument air, emergency diesel generator, and spent fuel pool cooling systems for the Peach Bottom, St. Lucie, Ginna, Millstone, and Pilgrim license renewal
applications. In addition, she was the principal investigator for the Browns Ferry and Oyster Creek license renewal application safety reviews. Ms. Green also performed an engineering evaluation of the severe accident mitigation alternative analysis required for license renewal for the following plants: Turkey Point, North Anna, Surry, Peach Bottom, McGuire, Catawba, St.
Lucie, Fort Calhoun, H.B. Robinson 2, Ginna, V.C. Summer, Dresden, Quad Cities, Farley, ANO-2, Browns Ferry, Millstone, Nine Mile Point, Brunswick, Monticello, Oyster Creek, Pilgrim, and Vermont Yankee. She participated in the onsite scoping and screening methodology audits at ANO-2 and Browns Ferry, and the aging management program/aging management review audit for Dresden and Quad Cities. in support of license renewal. Ms. Green has performed cost and regulatory analyses, specifically in support of the resolution of Generic Issue 189, for a modification to 10 C.F.R. § 50.44, and for a potential revision to 10 C.F.R. § 50.46 and 10 C.F.R. Part 50, Appendix K. In support of an effort to risk-inform byproduct and source material regulations, Ms. Green performed 14 cost-benefit analyses. She also reviewed two Combustion Engineering (CE) Owner's Group's submittals for extending the allowed outage time of the 125 Vdc and containment isolation valves, and provided input to the technical evaluation report.
From 1996 to 2000, at Scientech, Inc., Ms. Green performed risk analyses for byproduct material systems, including dose calculations and diamond tree analysis. She reviewed and characterized methodologies and codes cited in licensees UFSARs and licenses for incorporation in an NRC database. Ms. Green also reviewed D.C. Cooks containment sump design and performance after design basis accidents (DBAs), and she reviewed and characterized documents to support expert testimony on dose assessment and reconstruction.
As a contractor to the NRC, Ms. Green analyzed licensing commitments and regulatory requirements contained in the Millstone Unit 1 docket to develop an NRC database for the plants Current Licensing Basis (CLB).
From 1994 to 1996, at Digital Systems Research, Inc., later acquired by CACI, Ms. Green provided support to the Radiological Controls Program Advisor for Environmental Management at the U.S. Department of Energy (DOE) in the areas of radiological controls and health and safety. She reviewed and provided technical assessment of facilities' radiological protection programs for adequacy and compliance with applicable regulations (10 CFR 835, DOE Radiological Control Manual - DOE/EH-0256T, and DOE Order 5480.11).
From 1990 to 1994, at Bechtel Power Corporation, Ms. Green was a safety analysis engineer on the Steam Generator Replacement Core Team. In that capacity, she originated safety evaluations under 10 C.F.R. § 50.59 for mechanical and civil design modifications that required interface with engineers from multiple disciplines. She researched and developed position papers on the applicability of relevant regulatory issues such as long-term onsite storage of low-level waste, feedwater nozzle cracking/thermal stratification, leak-before-break, elimination of arbitrary intermediate breaks, and potential blockage of emergency core coolant system (ECCS) sump screens which required interface with industry organizations and other entities. She produced a technical study on various types of insulation used in containment at nuclear power plants. She also performed and reviewed mechanical calculations and nuclear design basis calculations dealing with radiation shielding and dose. She also provided safety analysis support to nuclear power utilities in Brazil and Spain regarding mechanical design modifications and steam generator replacement.