Advent's Project List

Advent Engineering Services, Inc.
Advent has performed the following projects for clients in the power industry: Design Basis Assistance and Configuration Control
  • Prepared and validated three design basis documents on post-accident sampling systems (PASS), main steam isolation valve leakage control system (MSIV-LCS), and remote shutdown system for a BWR plant (DE0001).
  • Performed validations of the Core Spray System and Reactor Manual Control System DBDs for a BWR plant (DE0002).
  • Prepared and validated comprehensive DBDs on fire protection (topical regulatory program and conventional fire protection systems) and hazards (seven hazards including: HELB, internal flooding, tornado, severe weather, industrial accidents, internal missiles, and external flooding) for a multi-unit PWR installations (WE0001).
  • Prepared topical DBDs for EQ and fire protection programs for a BWR plant (IE0203, IE0206).
  • Prepared the River Water Supply System DBD for a BWR plant (IE0204).
  • Prepared an electrical discipline topical DBD (IE0205).
  • Prepared a grid stability topical DBD (CP0001).
  • Prepared topical DBDs for EQ and station blackout programs for a multi-unit PWR (WE0004).
  • Prepared Pressurizer Pressure Control System DBD for a PWR plant (CP0006).
  • Prepared major revision to an Accident Analysis DBD for a two-unit PWR (SC0112).
  • Developed screening criteria and an implementation plan for determining which plant drawings are required to be kept up-to-date and which are required to be retained for historical purposes (IE0201).
  • Performed extensive research and developed a configuration control system for tracking the limiting values from accident analysis on a real time basis for a multi-unit PWR installation (SC0103).
Environmental Qualification
  • Performed a re-analysis of post-accident operating time qualification for equipment located inside containment, based on a new LOCA profile, for a PWR plant (FEDB13).
  • Developed qualification documentation for a PWR PORV (FEDB08).
  • Developed and implemented compensatory measures to assure the health of EQ equipment following an extended boric acid exposure (FEDB07).
  • Evaluated the effects of a Turbine Building HELB on the Operability of EQ Equipment in the Auxiliary Feedwater Pump Rooms in response to IN 2000-20 (FEDB05).
  • Provided technical support to engineering in responding to questions and findings during and following a comprehensive internal quality assurance audit of the EQ Program at a BWR plant (IE0101).
  • Performed engineering evaluations for the exclusion of equipment and justifications for continued operation of equipment subjected to the effects of a reactor water cleanup line break in the reactor building of a BWR plant (IE0103).
  • 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 technical review/update of plant environmental specifications including new methodology for detailed shielding calculations for localized beta doses to equipment at a BWR plant (IE0102).
  • Developed a "user friendly" approach for future updates of complying with 10 CFR 50.49 (EQ) requirements for aging assessments and performed aging assessments for equipment inside containment for a PWR plant (TE0003).
  • Performed a re-analysis of qualification for equipment located in HELB areas outside containment, based on new HELB profiles, for a PWR plant (TE0004, FEDB08). Required test report re-evaluation.
  • Developed four EQ file packages in a new format for a BWR plant (DE0004).
  • Performed a major update of basis for post-accident operating time for 102 EQ files (TE0003, TE0004, FEDB13).
  • Developed a detailed topical EQ program DBD which included a comprehensive description of the evolution of EQ regulatory requirements for a BWR plant (IE0203).
  • Developed 11 Mechanical EQ packages for a BWR plant (DE0020).
  • Participated on Management Consulting Team which reviewed EQ Program effectiveness at three CANDU nuclear stations (OH0001).
  • Prepared topical DBDs for EQ and station blackout programs for a multi-unit PWR (WE0004).
  • Provided on-site assistance to a "problem plant" to resolve EQ Program issues (SL0001).
10 CFR 50 Appendix R / Fire Protection
  • Provided Appendix R Fire Protection analysis, prepared basis documents, and electronic program documents for a single unit BWR plant (DE0035).
  • Assisted with NRC Triennial Fire Protection Inspection response (DE0035).
  • 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).
  • Reconstituted the Fire Protection and 10 CFR 50 Appendix R design bases for single unit BWR and multi-unit PWR plants (IE0206, WE0001, WE0003).
  • Validated the Fire Protection and Appendix R design bases for a multi-unit PWR plant (WE0001).
  • Resolved Fire Protection / Appendix R open items for a multi-unit PWR plant (WE0002).
  • 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 (WE0005).
  • Prepared topical DBDs for EQ and fire protection programs for a BWR plant (IE0203, IE0206).
  • Provided Appendix R Fire Protection consulting including analyses and calculations for a two-unit PWR (WE0005).
  • Prepared a fire protection system design change for the VA facility in Ann Arbor, Michigan (VA0001).
FSAR and Other Regulatory Compliance Support
  • Provided third party technical overview of a UFSAR review project at a two-unit PWR (SC0110).
  • Provided a detailed technical and regulatory compliance assessment of the UFSAR revision prepared as part of a client's validation project (SC0111).
  • Facilitated update of UFSAR through preparation of UFSAR change documents, technical reviews, and safety evaluations (DE0014).
  • Provided regulatory support to a client's Severe Accident Management Program including assessment of the effects on Emergency Operating Procedures and UFSAR (DE0021).
  • Provided a comprehensive review and comments on the conversion of a client's Technical Specifications to the Improved Technical Specifications format (NM0001).
  • Performed regulatory compliance consulting services for a research reactor facility (UM0001).
  • Prepared safety evaluations and licensing change requests in support of a major technical plant computer system (IPCS) modification. The new IPCS incorporated functions of nine, previously independent, digital processor systems and interfaced with seven additional systems. The mod also included control room and annunciator system upgrades (DE0023).
  • Developed living electronic UFSARs and companion electronic Operating License Technical Specifications and QA Topical Report for two separate nuclear units (NM0002).
  • Expanded living licensing basis electronic document library to include the plant SER (with Supplements) and applicable Regulatory Guides (NM0004).
Major Analyses and Engineering Evaluations
  • Analyzed the safety impact of a rupture of a reactor coolant pump's cooling coil on the operability of the component cooling water system for a PWR plant (SC0101).
  • 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).
  • Performed a complex calculation of the design heat load (radiative and convective heat transfer) for a PWR plant's biological shield cooling system (CP0001).
  • Analyzed the accumulated impact of plant modifications on LOCA peak clad temperature for a PWR plant (SC0101).
  • Performed a quantitative study to determine the feasibility of a safety injection system improvement modification for a PWR plant (SC0101).
  • 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).
  • 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).
  • Assisted a nuclear utility in evaluating the cost and value impact of developing a computerized cross-reference listing of design calculations (SC0103).
  • 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).
  • Prepared comprehensive design calculation revisions, engineering evaluations of existing conditions, and Safety Evaluations incident to updating the design bases for DC Electrical systems, the Emergency Equipment and Reactor Building Closed Cooling Water systems, and the Control Air system for a BWR plant (DE0003).
  • Provided on-site assistance at a nuclear utility in support of motor-operated-valve (MOV) set point and thrust calculations, evaluation of test results, analysis of signature traces, and evaluation of actual installation conditions in response to Generic Letter 89-10 requirements (SC0105, DE0006).
  • Developed and implemented a methodology for selective retention of strip chart recorder data for a nuclear utility in order to minimize the extent of hard copy retention (IE0202).
  • Prepared engineering analyses for reactor criticality, emergency diesel operability and room temperature on loss of HVAC (CP0003).
  • Prepared four major safety-related service and cooling water system design basis calculations (DE0007, DE0011.
  • Provided Appendix R Fire Protection consulting including analyses and calculations for a two-unit PWR (WE0005).
  • Developed a hydraulic computer model of a two-unit PWR Component Cooling Water System to verify two-unit shutdown capability for a single system (WE0005).
  • Developed a hydraulic computer model of a PWR Service Water System to verify safe shutdown capability under degraded conditions.
Quality Assurance Program Assistance
  • Developed and implemented an in-house 10 CFR 50 Appendix B/NQA-1 Quality Assurance Program, approved by four utilities, which includes heavy emphasis on training, flexible procedural controls, performance-based audits, and feedback mechanisms to identify opportunities for continuing improvement.
  • Performed a technical audit of a nuclear utility's fire protection program as a member of a QA audit team (TU0001).
  • Developed action plans and provided technical support during a nuclear utility's EQ regulatory inspection and subsequent programmatic audits (IE0101).
  • Facilitated update of UFSAR through preparation of UFSAR change documents, technical reviews, and safety evaluations (DE0014).
  • Provided technical support to a BWR plant during an NRC audit of the MOV Program (DE0008).
  • Provided technical expertise to a plant's QA staff for internal audits (DE0013).
Management Consulting and Third Party Reviews
  • Developed a comprehensive management action plan for improving the accuracy of drawings used by a BWR plant's control room operators (IE0201).
  • Assisted a management review team to evaluate and make recommendations concerning management practices at a nuclear utility having a station on the problem plant list (PR0001).
  • Facilitated benchmarking meetings with several diverse organizations for a nuclear utility working to upgrade its response to emergent work, comment resolution process, preparation of engineering procedures, development of calculations and engineering quality monitoring (SC0108).
  • Conducted a procedural effectiveness review for a nuclear utility's safety analysis (SC0107).
  • Provided third party technical overview of a UFSAR review project at a two-unit PWR (SC0110).
  • Participated on Management Consulting Team which reviewed EQ Program effectiveness at three CANDU nuclear stations (OH0001).
Design and Design Review
  • Prepared conceptual design and design modification for main generator and transformer high voltage fault relay protection system (TE0002).
  • Prepared a fire protection system design change for the VA facility in Ann Arbor, Michigan (VA0001).
  • Prepared a design change/construction specification package for a state of the art nurse call system for the VA facility in Battle Creek, Michigan (VA0002).