Dinesh Naik
Voorhees, NJ *****
***- ***-**** (H) 609 - 217 - 8418 (C)
Objective: Senior Mechanical Engineer position utilizing acquired engineering and interpersonal skills.
Education: B.S., Nuclear Engineering, University of Tennessee, 1982 Summary of current job responsibilities:
Over thirty years of experience in Nuclear Power industry. For past two years, assigned to Uranium Processing Facility for design of the HVAC systems for various buildings of the facility. Prior to this assignment, assigned to Watts Bar Nuclear Plant for Unit 2 for preparation of revision to existing calculations as well as preparing new calculations to support turnover efforts for Unit 2. The calculations involved various systems and subjects including Heating, Ventilation, and Air Conditioning, Failure Mode Analysis, High Energy line break, and hydraulic analysis of various systems. Experience Summary:
May 2011 – Present – Bechtel – Senior Mechanical Engineer Currently assigned to Uranium Processing Facility. Responsible for preparing HVAC system calculations, Airflow diagrams, Ventilation and Instrumentation diagrams, system design description document, and equipment specifications. Using Trane TRACE, prepared Airflow / Heating and cooling calculations for various buildings for the facility. Prepared Airflow Diagrams, V&IDs, and system design documents for the Mechanical / Electrical Equipment building HVAC system. Prepared equipment specification for exhaust fans for various buildings for the facility. Prepared data sheets for Air Filter Housings, Exhaust fans, and Electric Duct Heaters for Mechanical / Electrical Equipment building HVAC system. From May, 2011 to July 2015, assigned to Watts Bar Nuclear Plant Unit 2 Start-up project in Mechanical Calculation group. Responsible for preparing revision to existing calculations as well as preparing new calculation to support system turnover efforts for Unit 2. The calculations involved various systems and subjects including Heating, Ventilation, and Air Conditioning, Failure Mode Analysis, High Energy line break, and hydraulic analysis of existing piping system of various systems using TVA’s MULTIFLOW hydraulic analysis computer program. Revision to calculation also included removal of Unverified Assumptions by completing verification of the assumptions. The major calculations included ERCW Flow Balance using MULTIFLOW Program and CCS Heat Exchanger performance. Prepared System Descriptions for Auxiliary Building Heating and Ventilation system, Control Building Heating and Ventilation system, Emergency Gas Treatment System, Gaseous Waste Disposal System, Solid Waste Disposal System, and Liquid Waste Disposal System. Managed Flow Accelerated Corrosion program for Watts Bar Unit 2 that included selection of susceptible lines and their tracking.
March 2007 – May 2011 – Shaw Power Group – Senior Mechanical Engineer Prepared design modification package and associated support documents (10CFR50.59 and design calculation for vortex and head loss) to install ECCS Strainer for Beaver Valley Nuclear Plant. Prepared Engineering Reports for Main Steam, Extraction Steam system, Steam Generator Blowdown system, and Flow Accelerated corrosion program for Grand Gulf, Point Beach Nuclear Plant, and Surry Nuclear Plant to support Extended Power Uprate (EPU). The report also included preparation of pressure drop and velocity calculations to establish capability of system operation at higher flow, pressure, and Temperature. Dinesh Naik
25 Elliot Dr.
Voorhees, NJ 08043
2
Prepared Licensing Report (UFSAR update) for the Steam Generator Blowdown system, Light Load Handling system, and Flow Accelerated Corrosion Program for Point Beach Nuclear Plant to support the Extended Power Uprate.
March 1999 – March 2007 - Public Service Electric Gas, Nuclear LLC, Hancocks Bridge, NJ - System Engineer:
Responsible for managing Residual Heat Removal, Radioactive Waste, and Gas Turbine systems. My duties included performing system monitoring, maintaining system health reports and notebooks, system walk downs, developing long range plans, and champion the resolution of system issues - both short and long term. Troubleshoot equipment and system malfunctions. Initiated design changes to improve both, reliability of the system and reduce maintenance costs.
Maintenance Engineer:
Experience includes resolution of condition reports, deficiency reports for ASME vessels, preparation of Code Job Packages, Weld Joint Notices and Weld Histories. In addition, post maintenance test and test acceptance criteria were prepared for safety and non-safety related piping and components. Provided oversight of online & outage inspections of service water piping, valves & heat exchangers to support GL 89-13 program. Supported refueling outages for all service water inspection activities. October 1989 thru March 1999
Stone and Webster Engineering Corporation
Design engineer:
Experience includes preparation of design change packages for feedwater heaters replacement, MSR tube bundle replacement, and steam generator tube plugging for Salem Nuclear plant. For Hope Creek, several design changes for HPCI turbine, PCIG compressors, and Radwaste system. Preparation of design change packages included safety evaluation (10CFR50.59), bill of materials, and installation / test plans. Stationed at River Bend Nuclear Plant in Balance of Plant group of Design Engineering responsible for replacing service water system piping.
1983 thru October 1989
Tennessee Valley Authority, Knoxville, Tennessee
Design Engineer:
Performed spent fuel storage expansion study for Sequoyah and Browns Ferry Nuclear plants. Prepared system description documents for several systems including Radwaste and Chemical and Volume Control systems Sequoyah Nuclear plant. Supported refueling outage activities at both plants. Formal / Specialized Training:
Salem - Integrated Plant Operations Course (IPOC) – Nuclear Training Center, Salem, NJ Corrosion & MIC Seminar, Structural Integrity Associates, Inc. Salem System Engineer Training – Nuclear Training Center, Salem, NJ Operability Determination, GL 91-18
Maintenance Rule 10CFR50.65
Advance Repair Program