Responsibilities include writing calculations for modeling thermal hydraulic analyses for input in the GOTHIC computer software for both Design Engineering and Engineering Programs at nuclear operating plants. These analyses include determination of environmental parameters and evaluation of equipment qualification / operability / functionality within the given environment.

 

ANSI N45.23-1978 and NQA-1-1994 lead auditor activities include periodic evaluation and assessment of quality effectiveness of Tetra Tech Advent QA projects.

Performed engineering calculations in support of HELB analyses and Room Heat-Up analyses at Monticello and Prairie Island. Research in support of reconstituting EQ Program design basis requirements. Formulated and re establishing design requirements and bases in areas of EQ Master List control and EQ Program maintenance. Prepared numerous EQ file updates to reflect changes in normal and post accident temperature conditions. Participated in the evaluation of an EQ Program in support of Extended Power Uprate. Assisted in resolution of EQ condition reports identified at Davis-Besse during the boric-acid release event extended outage.

ANSI N45.23-1978 and NQA-1-1994 lead auditor activities include periodic evaluation and assessment of quality effectiveness of Advent QA projects. Performed 10 CFR 50.59 screens and evaluations as well as 50.59 Program audits and assessments

Assisted in the development of an approach and methodology for evaluating area temperature effects with respect to equipment aging and post-accident operability at a nuclear generating station. A generic approach for all EQ files was developed to simplify future program updates as well as EQ information retrieval to support maintenance. The engineering support tasks performed included a review of the client's existing program approach to equipment aging, a review of environmental stressors, comprehensive evaluation of individual equipment aging effects and operability, performing equipment-specific qualified life assessments based on thermal degradation, and developing and implementing recommendations for program development and qualified life extensions. Prepared or verified mechanical equipment EQ packages.

Participated in a project on the second phase of a nuclear station's EQ Program to address HELB steam flooding effects and resultant impact on post-accident operability.

Was also the primary reviewer for a design basis calculation for an emergency equipment cooling water (EECW) system. The calculation determined the amount of margin available for normal cooling water pump degradation over time resulting in lowered EECW system piping flows and decreased cooler heat removal capability. In addition to the EECW system, she was responsible for UFSAR and DBD updates for three additional related system design calculations including the residual heat removal service water system (RHRSW), emergency diesel generator service water system (EDGSW), and emergency equipment service water system (EESW).

As part of a safety analyses report (SAR) overview project team, assisted in resolving deviation events reports (DERs) written against numerous SAR sections. Prepared preliminary and safety evaluations for these DERs and providing the SAR revisions for incorporation.

Ms. Oshanski provided technical and analytical support for modifications to Iowa Electric's Duane Arnold Energy Center and Toledo Edison Company's Davis-Besse Station. These activities included: snubber reduction on Class 1, 2, and 3 piping systems, evaluations of valve operators in Class 2 and 3 piping, and design changes to HPCI and RCIC control valves, well water supply for drywell cooling modifications, and reactor water level indication.