Advent Engineering Services, Inc.

Licensing Project List
  • New Nuclear Services (DCD/COLA)
    • Assisted in the licensing, design, and design implementation of the first nuclear facility – [National Enrichment Facility (NEF), recently renamed as URENCO-USA] to be built in the US under the Combined Operating License (COL) process. To support this unique, innovative, complex project, provided several highly-qualified personnel on-loan for critical project roles at the construction site. These roles included Assistant Design Manager, Centrifuge Technology Field Mechanical Lead, Centrifuge Technology Pump-Set Project Manager, Autoclave Project Lead, Gaseous Effluent Ventilation System (GEVS) Milestone Manager, Nuclear-Mechanical System Design Lead (for GEVS and Compressed Air, Nitrogen, HVAC, and Alpha & HF Monitors), Central Utilities Building Project Lead, Site Utilities & Infrastructure Project Lead, Fire Protection Lead, and Integrated Door Design Lead (LES001).
    • Provided support to Fermi 3 Combined License Application (COLA) as follows: assisted in responding to US NRC Regulatory Information Summary 2007-08 on a Design Centered Review Approach for the Fermi 3 COLA; provided licensing expertise to support a Midwest client in an audit of the Fermi 3 COLA Environmental Report by the NRC and other external agencies; provided staff augmentation in support of timely responses for Fermi 3 COLA Requests for Additional Information from the NRC; provided on-loan Acting Manager of Licensing for Fermi 3 COLA Project; and provided consulting and engineering services to prepare the Michigan DNRE & USACE Joint Permit Application to support the Fermi 3 Environmental Impact Statement and COLA (BV0001, DE0138, DE0139, DE0140, DE0141, DE0142).
    • Provided licensing support and other technical assistance to Mitsubishi Heavy Industries (MHI) during the Pre-Application Review (PAR) phase of the US-APWR Design Certification. This project ended with the official docketing of the US-APWR Design Certification application in February 2008, and included the following key activities:
      • Participated in formal Pre-Application meetings with the NRC, principally meetings to describe the MHI Non-LOCA accident analysis methodology, including the computer codes used by MHI in the analysis of the events in Chapter 15 Design Control Document (DCD) (MHI001).
      • Created the Non-LOCA Methodology Topical Report for the US-APWR Chapter 15 DCD safety analyses. Technically edited and reviewed the initial draft of the English version of the MARVEL-M technical report for compliance with Standard Review Plan (NUREG-800) Section 15.02 and RG 1.203 and relevant NRC requirements. Supported the development of the US-APWR Diversity and Defense-in-Depth (D3) Coping Analysis and the MHI Reload Evaluation Methodology Technical Reports that were submitted to the NRC either in advance of or with the Design Certification Application. Supported an NRC audit of the DCD prior to its submittal to verify its completeness (MHI001).
      • Wrote Chapter 15 of the US-APWR DCD (non-LOCA analysis). Reviewed the completed deliverable for compliance with NRC requirements, applicable regulatory guidance, and standard practices in the US, e.g., US industry standards and the EPRI Utility Requirements Document (URD) (MHI001).
      • Presented written and verbal US-APWR licensing material to the NRC on behalf of MHI (MHI001).
      • Assisted MHI in making critical design changes to the US-APWR design to meet US NRC requirements, US Utility requirements, Standard Review Plan (NUREG-800), Regulatory Guides, and US national industry standards (MHI001).
    • Provided licensing support of the accident analysis (DCD Chapter 15) portion US-APWR Design Certification Application from formal docketing to NRC Safety Evaluation Report and ACRS review. This project also included support of MHI in developing the Emergency Response Guidelines ERGs), Standard Emergency Procedures (SEOPs) and associated Background Documents for the US-APWR standard design, as well as assisting MHI in licensing and design activities to introduce designs to the European market (EU-APWR). This project included the following specific activities:
      • Provided Request for Additional Information (RAI) support for NRC approval of MHI’s US-APWR DCD Chapter 15 (Safety Analysis). Relevant support included representing licensee at teleconference and face-to-face meetings, preparing RAI response drafts, and reviewing licensee documents for technical clarity, completeness, and grammatical correctness prior to NRC submittal (MHI002, MHI003, MHI005).
      • Presented the Non-LOCA Methodology Topical Report to the ACRS in a public meeting (MHI002, MHI003, MHI005).
      • Provided RAI support for NRC approval of MHI’s US-APWR Non-LOCA Methodology Topical Report (MHI002, MHI003, MHI005).
      • Provided strategic advice on RAI preparation and back up documentation based on NRC review activity and US nuclear industry trends (MHI002, MHI003, MHI005).
      • Created new technical reports (such as Procedure Development Implementation Plan) and provided reviews of Technical Reports and associated revisions drafted by MHI (such as the Reload Methodology Topical Report) to support US-APWR licensing efforts (MHI002, MHI003, MHI005).
      • Provided technical guidance and expertise in the preparation of necessary COL documentation, including RAI responses, Emergency Response Guidelines (ERGs), Standard Emergency Operating Procedures (SEOPs) with supporting training background documents, and Technical Specifications. The ERG & SEOP development also included developing special procedures and associated background documents for plant shutdown using only safety controls and plant shutdown using the Diverse HSI (Human System Interface) Panel (MHI002, MHI003, MHI005).
      • Provided RAI support for NRC approval of MHI’s US-APWR Defense-in-Depth and Diversity (D3) Topical Report and corresponding Defense-in-Depth and Diversity Coping Analysis Technical Report (MHI002, MHI003, MHI005).
      • Created English versions of the US-APWR safety analysis code manuals for MHI internal use and NRC review (MHI002, MHI003, MHI005).
      • Provided licensing support for the development and licensing of new MHI designs for deployment in the European market (EU-APWR) in accordance with the requirements of European regulators and the European Utilities Requirement document(MHI002, MHI003, MHI005).
    • Provided licensing support of the radiological portion of DCD Chapter 15 and the Chapter 11 and 12 Radiation Protection Program portion US-APWR Design Certification Application from formal docketing to NRC Safety Evaluation Report and ACRS review. This project included the following specific activities: Provided Request for Additional Information (RAI) support for NRC approval of MHI’s US-APWR DCD Chapters 11 (radioactive waste), 12 (dose), and 15 (radiological analysis portion of the safety analysis). Relevant support includes representing licensee at teleconference and face-to-face meetings, preparing RAI response drafts, and reviewing licensee documents for technical clarity, completeness, and grammatical correctness prior to NRC submittal (MHI004, MHI006).
    • Provided support to MHI’s US wholly-owned subsidiary (MNES) to support Combined License Applications referencing the certified US-APWR design, including:
      • Provided technical support and expertise in assisting MNES in the preparation of licensing documentation (DCD/COLA) for the US-APWR and in the response of the subsequent RAIs from the NRC (MNES01).
      • Provided technical support to MNES and their US licensees prior to and during regulatory meetings with the NRC (MNES01)
    • Drafted the "Professional Services" section of the Engineering/Procurement (EP) Technical Package for the US-APWR at Comanche Peak Units 3 and 4 in support of the new-build project contract development (MNES02)
  • Licensing Basis / Regulatory Compliance
    • Provided technical support to a BWR plant during an NRC audit of the MOV Program (DE0008).
    • Provided on-site assistance to Fermi licensing on Oscillation Power Range Monitor Tech Spec Change and other licensing issues (DE0009).
    • Facilitated update of UFSAR through preparation of UFSAR change documents, technical reviews, and safety evaluations (DE0014).
    • On-site support to licensing and regulatory compliance. (DE0016, DE0017)
    • Provided regulatory support to a client's Severe Accident Management Program including assessment of the effects on Emergency Operating Procedures and UFSAR (DE0021).
    • Provided on site support to the Independent Safety Evaluation Group at Fermi 2 (DE0022).
    • Performed research and developed recommendation for resolution of ECCS Suction Strainer issue (DE0026).
    • Performed pre-NRC inspection assessment of the fire protection program at Fermi 2 (DE0029).
    • Assessed, developed design change recommendations, and validated operator manual actions required for design basis fire scenarios (DE0045).
    • Developed a "white paper" to document reactor building crane lift capacity and to evaluate upgrade options (DE0070).
    • Performed updates of licensing basis documents for modification of the spent fuel pool cooling system (DE0113).
    • Provided a comprehensive review and comments on the conversion of a client's Technical Specifications to the Improved Technical Specifications format (NM0001).
    • 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).
    • Prepared a chronological history of the analysis of record for each of the UFSAR Chapter 15 accidents (approximately 40 total) for a West Coast PWR (SCO0102).
    • Developed a list of assumptions related to ESFAS instrument errors for the purpose of developing uncertainty analyses based on the instruments used to maintain a West Coast PWR within its licensed limits (SCO104).
    • 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).
    • Performed regulatory compliance consulting services for a research reactor facility (UM0001).
    • Acted as nuclear industry expert member of both the University of Michigan Ford Nuclear Reactor (FNR) Safety Review Committee and Decommissioning Review Committee (UM0004).
    • Performed research of applicable piping drawings and provided input to Design Engineering’s response to Generic Letter 08-01 (NMPI102).
    • Provided on-site support in preparation for and during Component Design Basis Inspection (CDBI) at Prairie Island (NMPI13).
    • Provided guidance and expertise in interpreting documents pertaining to Licensing Bases and Commitments, Plant System and Equipment Functions and locations, and Plant Design in accordance with the Site change processes and Q-List Project Procedures (NMPI18).
  • License Renewal
    • Performed independent review of approximately 100 EQ package revisions performed for license renewal and miscellaneous minor change notices (FEDB18, FEDB19).
    • 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).
    • Prepared more than 40 Environmental Reports in support of US Nuclear Power Plant License Renewal Applications (Advent sister company NUS)
  • Power Uprate
    • Developed recommendations for updating EQ program in preparation for Extended Power Uprate (EPU) (DE0036).
    • Reviewed and provided recommendations for impact of EPU on Fire Protection Program (DE0042).
    • Provided augmented staff support to the Systems Engineering department in support of EPU and other site projects (NMO02).
  • Decommissioning
    • Assisted a client in developing an action plan for decommissioning of a New England Reactor, including disposition of spent fuel (BE0001).
    • Acted as nuclear industry expert member of both the University of Michigan Ford Nuclear Reactor (FNR) Safety Review Committee and Decommissioning Review Committee (UM0004).
    • Performed structural analysis of the University of Michigan Ford Nuclear Reactor building enclosure in support of decommissioning (UM0005).
  • Emergency Operating Procedures (EOPs)
    • Provided regulatory support to a client's Severe Accident Management Program including assessment of the effects on Emergency Operating Procedures and UFSAR (DE0021).
    • Provided technical guidance and expertise in the preparation of necessary COL documentation, including RAI responses, Emergency Response Guidelines (ERGs), Standard Emergency Operating Procedures (SEOPs) with supporting training background documents, and Technical Specifications. The ERG & SEOP development also included developing special procedures and associated background documents for plant shutdown using only safety controls and plant shutdown using the Diverse HSI (Human System Interface) Panel (MHI002, MHI003, MHI005).
    • Provided an assessment of time critical operator actions in preparation for Component Design Basis Inspection (CDBI) at Prairie Island (NMPI13).
    • 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).
 
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