Advent Engineering Services, Inc.

Program Project List
  • Equipment Qualification
    • Performed independent analysis of Hoppecke OSP.XC and OSP.HC batteries to demonstrate the the OSP-HC is sufficiently similar to OSP.XC, and meets the same relevant qualification requirements of specific aging and seismic related IEEE standards (CT0003).
    • Developed four EQ file packages in a new format for a BWR plant (DE0004).
    • Developed 11 Mechanical EQ packages for a BWR plant (DE0020).
    • Developed recommendations for updating EQ program in preparation for Extended Power Uprate (EPU) (DE0036).
    • Reviewed and provided recommendations for impact of EPU on Environmental Qualification Program (DE0041).
    • In support of Alternate Source Term implementation, developed approach for showing qualification of the Fermi Standby Liquid Control System (DE0047).
    • Developed EQ File for AVCO MSIV pilot solenoid valves (DE0054).
    • Provided input, consultation, technical assessment, and independent perspective, to the task force evaluating potentially heat damaged equipment and cable in the steam tunnel (DE0056).
    • Prepared EQ file revision to address fuse blocks (DE0068).
    • Provided technical support during plant shutdown, in the form of analysis of impact on EQ equipment, caused by drywell cooler degraded performance. Subsequently participated on the root cause team (DE0076).
    • Developed EQ Program improvement project plan (DE0078).
    • Performed EQ acceptability design verification of Power Module Voltage Regulator Design Modification (DE0089).
    • Prepared six Raychem EQ files and associated EQ Maintenance & Surveillance Letters (DE0090).
    • Prepared seven EQ files for the following equipment: Exo-Sensors, 3M Scotch, Barton Switches, Hoffman Terminal Blocks, ITE Gould MCC, Westinghouse Motors, and Buchanan Fuse Blocks (DE0097).
    • Assessed and updated EQ files to address a revision of the small break LOCA analysis, which increased the HPCI operating time from 1 to 3 hours at a midwest BWR (DE0111).
    • Updated Limitorque MOV and Pyco RT EQ Files at a Midwest BWR (DE0125).
    • Evaluated the Impact of Tefzel Tie Wrap Degraded Material (DE0130).
    • Performed third party review of EQ documentation for Barton Pressure Switches used in Torus Vacuum Breaker application (DE0135).
    • Updated EQ Program at Midwest PWR to incorporate 13 years of normal containment temperature data. This included EQ File and Maintenance Program updates (FEDB04).
    • 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).
    • Performed evaluation demonstrating acceptability of potentially submerged Kerite insulated cable based on time elapsed (FEDB06).
    • Developed and implemented an action plan to assure the health of EQ equipment following an extended boric acid exposure (FEDB07).
    • Developed qualification documentation for a PWR Power Operating Relief Valve (PORV) (FEDB08).
    • 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).
    • Performed thermal time lag analysis to justify continued qualification following increased HELB temperature profiles (FEDB09).
    • Evaluated new conditions and past operability for a Midwest PWR's updated turbine building HELB conditions (FEDB10).
    • Developed EQ package for Framatome Fuse Disconnects (FEDB11).
    • Created / updated EQ packages for High Pressure Injection Pump Minimum Flow Mod (FEDB12)
    • 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).
    • Performed evaluation to exempt 14 Molded Case Circuit Breakers from EQ Program by consideration of HELB effects (FEDB14).
    • Evaluated and resolved test anomalies for Fused Disconnect Switches (FEDB15).
    • Performed independent review and validation of EQ Master List (FEDB16).
    • Assisted a client in reviewing 56 EQ Package Change Notices (EQPCNs) for a Midwest PWR (FEDB17).
    • Performed independent review of approximately 100 EQ package revisions performed for license renewal and miscellaneous minor change notices (FEDB18, FEDB19).
    • Developed EQ documentation for replacement Reactor Core Isolation Cooling Controllers at a Midwest BWR 6 plant (FEPY01).
    • Performed independent review of the licensing and design basis for high energy line breaks at a Midwest BWR (IE0001).
    • 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).
    • 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).
    • 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).
    • Prepared detailed topical EQ Program DBDs (which included a comprehensive description of the evolution of EQ regulatory requirements) for both BWR and multi-unit PWR plants (IE0203, NMKE02, WE0004).
    • Participated on Management Consulting Team which reviewed EQ Program effectiveness at three CANDU nuclear stations (OH0001).
    • Provided on-site assistance to a "problem plant" to resolve EQ Program issues (SL0001).
    • 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 major update of basis for post-accident operating time for 102 EQ files (TE0003, TE0004, FEDB13).
  • Appendix R/Fire Protection
    • 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).
    • Prepared calculation to demonstrate that the plant can obtain cold shutdown conditions within 72 hours of an evaluated fire scenario (CP0004).
    • Provided 1.5 day Appendix R training for new Fire Protection Lead (CP0005).
    • Performed fire hazards evaluation for integrated plant computer system project (DE0023).
    • Performed as-built inspection of penetration seals against design requirements (DE0026).
    • Performed as-built walkdowns of fire suppression sprinkler system for NFPA 13 and 72D compliance with code requirements for Fermi 2 (DE0027, DE0033).
    • Performed design verification of associated circuits analysis for Fermi 2 (DE0028).
    • Performed pre-NRC inspection assessment of the fire protection program at Fermi 2 (DE0029).
    • Developed comprehensive Get Well Plan for Fire Protection Program at Midwest BWR (DE0034).
    • Provided Appendix R Fire Protection analysis, prepared basis documents, and electronic program documents for a single unit BWR plant in preparation for a NRC inspection (DE0035).
    • Reviewed and provided recommendations for impact of EPU on Fire Protection Program (DE0042).
    • Assessed, developed design change recommendations, and validated operator manual actions required for design basis fire scenarios (DE0045).
    • Provided technical support for a response to a congressional inquiry on fire protection and manual operator actions (DE0047).
    • 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).
    • Provided engineering support for time line development, root cause analysis and other technical assistance, as required, to resolve a Level 1 CARD regarding design procedural deficiencies affecting the dedicated shutdown scenario (DE0075).
    • Performed fire modeling for fire detection system response (DE0084).
    • Developed and reviewed 50.59 documents and fire protection program impact assessment documents for improvements to the Radwaste Switchgear Room Cooler (DE0100).
    • Assessed fire detectors for code compliance and provided recommendations for resolution of issues identified (DE0111, DE0117, DE0120).
    • Performed analysis of functionality of instrument sensing lines for exposure to design basis fires (DE0137).
    • Provided SFPE Member / Fire Protection Technical Specialist to support Nuclear Plant Owner Triennial Fire Protection Audit (DK0001, DK0002, DOM001, TV0001).
    • Prepared and validated comprehensive DBDs on fire protection (topical regulatory program and conventional fire protection systems). Reconstituted the Fire Protection and 10 CFR 50 Appendix R design bases for single unit BWR and multi-unit PWR plants. Included resolution of identified design basis issues (IE0206, IE0207, IE0208, WE0001, WE0003).
    • Performed a technical audit of a nuclear utility's fire protection program as a member of a QA audit team (TU0001).
    • Prepared a fire protection system design change for the VA facility in Ann Arbor, Michigan (VA0001).
    • Resolved Fire Protection / Appendix R open items for a multi-unit PWR plant (WE0002).
    • 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).
    • While On-Loan as NEF Fire Protection Design Lead (LES001)
      • Supported Integrated Safety Analysis Team as fire protection representative
      • Reviewed and approved procurement specifications for fire water storage tanks, fire water pump house, underground fire main system, fire protection sprinkler systems, fire protection standpipe systems, and fire detection and alarm systems
      • Reviewed and approved fire detection and alarm designs for all major site structures
      • Reviewed and approved fiber optic data loop for site fire alarm system
      • Reviewed and approved fire suppression system designs for all major site structures
      • Reviewed and approved portable fire extinguisher plans for all major site structures
      • Reviewed and approved personnel egress plans for all major site structures
      • Created Combustible Loading Calculation for structures containing radioactive material
      • Created Fire Hazards Analysis document for structures containing radioactive material
      • Updated fire protection sections of the site Safety Analysis Report and the Integrated Safety Analysis Summary
      • Provided technical inputs to designs of fire-related Items Relied Upon for Safety (IROFS)
      • Provided technical interface with the Office of the State Fire Marshal
      • Provided technical interface with the US Nuclear Regulatory Commission (NRC) Region II Fire Protection Inspector
      • Assisted Commissioning and Acceptance engineers in developing test procedures for the site fire main and building sprinkler systems
      • Assisted Operations personnel in developing periodic test and surveillance procedures for the site fire main, building sprinkler systems, and building fire alarm systems
      • Provided overview of fire detection and fire protection contractors during installation.
  • Quality Assurance
    • Developed and implemented an in-house 10 CFR 50 Appendix B / NQA-1 Quality Assurance Program which includes heavy emphasis on training, flexible procedural controls, performance-based audits, and feedback mechanisms to identify opportunities for continuing improvement (AES0001).
    • Performed independent evaluation of future usefulness and long term cost-effectiveness of Callaway's upper level design basis document (ULDBD) Project as part of Callaway's internal self assessment program (AUE001).
    • Provided technical expertise to a plant's QA audit of a major General Service Water System design modification (DE0013).
    • Developed action plans and provided technical support during a nuclear utility's EQ regulatory inspection and subsequent programmatic audits (IE0101).
    • Performed a technical audit of a nuclear utility's fire protection program as a member of a QA audit team (TU0001).
    • Researched open Engineering Change (EC) items, Corrective Action Program (CAP) items, and 50.59 Screenings for Prairie Island's Engineering Recovery Project (NMPI15).
    • Performed a third party assessment of inordinately high number of field change requests and field questions occurring at a new nuclear facility being constructed (LES001).
  • Aging Management
    • Performed evaluation demonstrating acceptability of potentially submerged Kerite insulated cable based on time elapsed (FEDB06).
    • Developed and implemented an action plan to assure the health of EQ equipment following an extended boric acid exposure (FEDB07).
    • 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).
    • While on-site as acting supervisor of electrical and I&C systems engineering, provided guidance on implementation of electric cable condition monitoring program (NMP017).
    • Chaired the Working Group adapting IEEE Std 1205 to provide guidance for License Renewal aging management. Specifically developed the thermal and radiation aging assessment methodology, created a new model for non-constant temperature conditions, and created an annex for condition monitoring approaches for many types of equipment including electric cable. As a result, IEEE Std 1205 is a reference in the NRC’s Generic Aging Lessons Learned Report (AES1205).
  • 50.59 / 70.72
    • Prepared safety evaluations (now called 10CFR50.59 evaluation) and licensing change requests in support of a major technical plant computer system (IPCS) and annunciator system 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, DE0030, DE0037, DE0063).
    • Performed 50.59 review of 120kV switchyard design modification project (DE0040, DE0077).
    • Prepared 10 CFR 50.59 documentation and licensing change requests for major security modifications being performed (DE0048).
    • Provided on-site 10 CFR 50.59 review specialty service. These reviews not only showed technical adequacy but also assured consistency with other screens and evaluations being done (DE0032, DE0053, DE0103, DE0124, DE0127).
    • Developed licensing change request and 50.59 documents to support moisture separator reheater replacement (DE0060).
    • Prepared and reviewed 50.59 documents for major modification to the refueling bridge platform at a Midwest BWR (DE0066).
    • Prepared and reviewed 50.59 documents for modifications to the installed R-C circuits to reduce or eliminate spurious alarms (DE0069).
    • Prepared and reviewed 50.59 documents for the setpoint changes to the EECW pump differential pressure instrument (DE0073).
    • Established effectiveness review criteria for security impacts and prepared design input requirements in 50.59 documents for modifications to the secondary alarm station (SAS) security building (DE0080).
    • Developed and reviewed 50.59 documents for RHR pump seal cooler system modification (DE0081).
    • Developed and reviewed 50.59 documents for load testing and operation of Barnhart Main Lift Tower and Turbine Building Cranes for moisture separator reheater movement (DE0082).
    • Developed and reviewed 50.59 documents for as-built change to turbine building shield walls (DE0087).
    • Performed fire protection program assessment and 50.59 documents for Safety Relief Valve nitrogen supply modification for a Midwest BWR (DE0094).
    • Developed and reviewed 50.59 documents for Refueling Bridge hardware and software changes (DE0096).
    • Developed and reviewed 50.59 documents for Transformer 2B replacement and related changes to deluge system (DE0099).
    • Developed and reviewed 50.59 documents and fire protection program impact assessment documents for improvements to the Radwaste Switchgear Room Cooler (DE0100).
    • Developed and reviewed 50.59 documents for changes to cathodic protection (DE0101).
    • Prepared 50.59 documents and FMEA for Motor Generator Scoop Tube Upgrade (DE0102, DE0123, DE0136).
    • Developed and reviewed 50.59 documents for Emergency Equipment Cooling Water Pump Replacement Project (DE0106).
    • Developed and reviewed 50.59 documents for 345 kV Switchyard GPS Clock Project (DE0122).
    • Developed and reviewed 50.59 documents for 345 kV Switchyard Protective Relaying Modification Project (DE0126).
    • Developed and reviewed 50.59 documents for Design Changes to MOV Thermal Overload Relays (DE0128).
    • Developed and reviewed 50.59 documents for Division 1 & 2 Hot Deck Low Temperature Switch Setpoint Change (DE0131).
    • Developed and reviewed 50.59 documents for Diesel Generator Service Water Pump Status Inaction Design Change (DE0132).
    • Developed and reviewed 50.59 documents for Balance-of Plant Battery Charger High Voltage Shutdown Setting Change (DE0133).
    • Provided various engineering support to the Design Engineering department, including 50.59s, independent review, diesel calculations and civil calculations (NMPI01).
    • Researched open Engineering Change (EC) items, Corrective Action Program (CAP) items, and 50.59 Screenings for Prairie Island's Engineering Recovery Project (NMPI15)
  • MOV / AOV
    • 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).
    • Provided technical support to a BWR plant during an NRC audit of the MOV Program (DE0008).
    • Provided on-site MOV program assistance to Fermi (DE0010).
    • Developed and reviewed 50.59 documents for Design Changes to MOV Thermal Overload Relays (DE0128).
    • 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).
    • While on-site as acting supervisor of electrical and I&C system engineering, developed an innovative, cost effective approach for addressing motor overload relays (NMP017)
  • Nuclear Training
    • Provided 1.5 day Appendix R training for new Fire Protection Lead (CP0005).
    • 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).
    • Developed and administered training on 10 CFR Part 21 (TE0005).
    • Performed Component Design Basis Inspection (CDBI) at Prairie Island. Subsequently provided regular team and individual training in the engineering approach to problem solving and appropriate acceptance criteria identification (NMPI13).
 
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