- Thermal Hydraulic
- Performed a complex calculation of the design heat load (radiative and convective heat transfer) for a PWR plant's biological shield cooling system (CP0001).
- Prepared four major safety-related service and cooling water system design basis calculations (DE0007, DE0011.
- Provided analytical and design support to Emergency Equipment Cooling Water (EECW) System (DE0015).
- Provided results of an analysis of RHRSW and cooling tower upset temperatures (DE0018).
- On-site support to perform additional analysis in support of a new design basis scenario for the ultimate heat sink calculation at Fermi 2 (DE0024).
- Performed design verification of revisions performed on Fermi's ultimate heat sink and essential service water system design calculations (DE0039, DE0050).
- Analyzed the conditions under which the pressurizer may be vented following a plant shutdown to assure core cooling with loss of the decay heat removal system for a PWR plant (SC0103).
- Analyzed the impact of a high containment pressure instrument set point change on the containment peak pressure following a main steam line break for a PWR plant (SC0106).
- Constructed a hydraulic model of the fire protection water supply system for a multi-unit PWR plant and analyzed the system response to particular scenarios of interest and to verify two-unit shutdown capability for a single system (WE0005-5).
- Provided the day–to-day services of the High Energy Line Break (HELB) engineer, including providing engineering guidance and expertise in reviewing documents and corrective actions related to the HELB Program (NMO05).
- Performed sensitivity studies on the plant’s GOTHIC HELB model to determine the impact of a previously unanalyzed HELB interaction with the Component Cooling Piping (NMPI04).
- Performed sensitivity studies on the plant’s GOTHIC HELB model to determine the impact of a modification that added new fire doors (NMPI05).
- Created a new calculation to model HELB in the Turbine Building, and revised additional calculations that are inputs to the HELB calculation (NMPI07).
- Performed design verification on the HELB selection calculation (NMPI08).
- Performed GOTHIC HELB model modifications in support of the emergency diesel operability determination process (NMPI09).
- Performed HELB analysis using GOTHIC for the Prairie Island Turbine Building. (NMPI10).
- Provided thermal hydraulic analysis support in a plant's response to a regulatory violation related to flooding following HELBs (NMPI11).
- Performed GOTHIC based sensitivity study on the HELB analysis to document the effects of a new wall penetration in the Turbine Building due to modification being made to install new station air compressors at Prairie Island (NMPI14).
- Provided a safety-related GOTHIC calculation that documented the effect on the environmental conditions of the planned addition of openings in the Turbine Building and documented how these potential changes impact the HELB analysis (NMPI20).
- Stress Analysis
- Reviewed and resolved a complex structural rebar (exceeding allowable stress) issue affecting all walls in a major enclosure building (LES001).
- Performed structural calculation for the concrete support bed in preparation for a major power plant replacement component (IE1005).
- Performed design verification of numerous structural calculations for Midwest PWR (NMPI01, NMPI03).
- Prepared white paper confirming that the effect of the test equipment load would remain below code allowable with a Trevitest device on the main steam safety relief valves. This test configuration consisted of a temporary replacement of the safety relief valve cap with a test rig device and adapter, which would weigh more than the existing valve cap (NMPI01).
- Developed a "white paper" to document reactor building crane lift capacity and to evaluate upgrade options (DE0070).
- Loss of HVAC Analysis
- Prepared engineering analyses for reactor criticality, emergency diesel operability and room temperature on loss of HVAC (CP0003).
- Provided spreadsheet-based computer models for eight Appendix R room heat models (CP0007).
- Prepared heat-up calculation to analyze Balance-of-Plant Chiller Compressor trip in DC MCC Room (DE0088).
- Performed room heat up calculations for beyond design basis scenarios involving loss of HVAC in support of future risk significance assessments (DE0104, DE0114, DE0118).
- Analyzed vent paths related to HELBs in the torus room to refine and reduce conservative dose rate assumptions in critical areas of the reactor building affected by steam flooding (IE0104).
- Provided support to the Prairie Island Calculation Reconstitution and Improvement Project, including calculation mapping and creation of room heat-up calculations. (NMPI03).
- Performed Room Heat Up Analysis using GOTHIC for the Prairie Island Turbine Building and Diesel Generator Rooms. The analysis created new thermal hydraulic and civil calculations to be used in PRA (NMPI12).
- Accident Analysis
- Developed a list of assumptions related to Engineering Safeguard Features Actuation System (ESFAS) instrument errors for the purpose of developing uncertainty analyses based on the instruments used to maintain the West Coast PWR within its licensed limits (SCO104).
- Developed, reviewed and provided training of Margin Allocation Records for each accident safety analysis for a West Coast PWR (SCO107, SCO109).
- Prepared major revision to an Accident Analysis DBD for a two-unit PWR (SC0112).
- Prepared and validated hazards DBD (seven hazards including: HELB, internal flooding, tornado, severe weather, industrial accidents, internal missiles, and external flooding) for a multi-unit PWR installation (WE0001).
- Prepared topical DBDs for station blackout program for a multi-unit PWR (WE0004).
- Dose Assessment
- Performed Low Pressure Turbine Rupture Disk Radiation Dose Calculation and Material Assessment (DE0129).
- Analyzed the accumulated impact of plant modifications on LOCA peak clad temperature for a PWR plant (SC0101).
- Probabilistic Risk Assessment (PRA)
- Performed a failure mode effects analysis (FMEA) on the high pressure safety injection system for a PWR plant (CP0001).
- Performed a quantitative study (mini-PRA) which verified the probability of tornado missile damage to key safe shutdown systems at a BWR plant (DE0003).
- Performed calculations and generated documentation in support of Fermi 2 success criteria for HPCI, RCIC, EDGs, and RHR / RHRSW in the form of draft PRA sections of the Fermi 2 Mitigating System Performance Indicator (MSPI) basis document (DE0071).
- Prepared FMEA for Motor Generator Scoop Tube Upgrade (DE0102, DE0123, DE0136).
- Provided support to a Federal Aviation Administration Aircraft EIS Risk Model Project (LM0001).
- Performed equipment evaluation for elevated temperature environments to support the PRA model (NMO03)
- Performed sensitivity study of the Monticello PRA model (NMO04).
- Provided guidance and expertise in improving the Monticello PRA program to meet Regulatory Guide 1.200 Standards (NMO06).
- Provided PRA support in implementing Regulatory Guide 1.200 (including the CAFTA models) and performing Significance Determination Process Evaluations (NMPI11).
- Performed pre-closure safety analysis for Yucca Mountain project (YM0001).
- Performed independent safety analysis review for Yucca Mountain Project (YM0002).
- Safe Shutdown Analysis
- Prepared calculation to demonstrate that the plant can obtain cold shutdown conditions within 72 hours of an evaluated fire scenario (CP0004).
- Prepared a comprehensive calculational report which updated the design basis and analyzed post-LOCA and design basis tornado operability for a BWR plant's ultimate heat sink system, which required extensive research on ultimate heat sink related regulatory requirements and commitments as well as analysis (DE0003).
- Consolidated the design basis requirements for the Remote Shutdown System at Fermi 2 into a single controlled document (DE0005).
- Performed design verification of associated circuits analysis for Fermi 2 (DE0028).
- Prepared an Abnormal Operating Procedure for plant fires, providing detailed shutdown guidance for fires that did not require evacuation of the Control Room. Included was a basis document detailing the basis and methodology for critical Control Room actions, manual actions outside the Control Room and required shutdown repairs. In addition, a Fire Protection Engineering Evaluation was prepared to meet NRC requirements to demonstrate feasibility of manual action taken outside the Control Room. A classroom training course was also prepared to train operators on fire response action inside and outside the Control Room (DE0064).
- Assisted with the 10 CFR 50 Appendix R safe shutdown rebaseline analysis for both single unit and multi-unit PWR plants, including preparation of calculations to quantify the amount of time available to mitigate the effects of predetermined faults and writing the top-level documents used as guidance by plant operators and managers (CP0003, WE0005).
- Constructed a hydraulic model of the fire protection water supply system for a multi-unit PWR plant and analyzed the system response to particular scenarios of interest and to verify two-unit shutdown capability for a single system (WE0005-5).
- Emergency Planning/Evacuation
- Updated population and access route data surrounding a Midwest BWR (DE0031).
- Modeled and performed real-time interpretation of an evacuation for a Midwest BWR and its surrounding area using OREMS (DE0031).
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