Safety, Licensing & Regulatory Analysis
·
Lead Systems Analysis Analyst supporting the
Risk Goal Quantification, probabilistic Authorization Basis analysis, of the
all facilities and radiological risks at the River Protection Project –Waste
Treatment Plant, RPP-WTP.
·
Familiar with the Authorization Basis of the
RPP-WTP. Performed AB Maintenance
compliance evaluations for proposed design changes of the RPP-WTP.
·
Participated in revision and update to
incorporate safety system modification and contractor reorganization for the
Hanford Tank Farms SAR and to update the safety management portions of the
Radiochemistry Processing Laboratory (RPL) SAR.
Both of these SARs meet the requirements of DOE Order 5480.23. He participated in an assessment to determine
readiness to implement the previous revision of the RPL SAR, which implemented
TSRs for the first time in this Category 2 Nuclear Facility. Qualified as USQ reviewer for the RPL SAR.
·
Involved in the combined DOE-NE/DOE-ID review of
the Upgraded Final Safety Analysis Report (SAR) for the ATR, a 250 MW
light-water-cooled, aluminum-matrix-fuel test reactor located at the Idaho
National Engineering Laboratory (INEL).
The overall review of this SAR (to DOE Order 5480.23 requirements)
involved 15 DOE-HQ, DOE-ID, and LITCO personnel. Task involved assisting DOE-ID in
establishing the review plan, procedures, and safety evaluation report (SER)
format and reviewing portions of the SAR, including the executive summary, the
Technical Safety Requirements (TSR) Derivation Chapter, and the TSRs. Wrote the SER section that addresses the TSR
derivation and the TSRs.
·
Involved in the resolution of review comments on
the Final Safety Analysis Report for the Waste Storage Facilities, which were
under construction at the Radioactive Waste Management Complex (RWMC) at the
INEL. The task involved coordinating
between DOE‑EM reviewers in Germantown and
the FSAR authors at the RWMC, including attendance at resolution working
meetings in Germantown
and at the INEL. The SER was completed
and operation was authorized by DOE‑EM.
This task also involved review, comment resolution, and drafting the SER
for the Waste Characterization Facility Preliminary Safety Analysis Report.
Regulatory Oversight
·
Completed four years with DOE‑RL
performing oversight and review of contractor safety analysis tasks associated
with new facilities and modifications to existing facilities for the removal of
spent fuel to dry storage.
Responsibilities included USQ Oversight and Authorization Basis
Maintenance compliance. This project is
applying DOE Order 5480.23 and selected NRC safety criteria to phased
construction of storage and conditioning facilities and equipment. Provided coordination of onsite and offsite
reviewers, consolidated comments, and assisted in safety evaluation report
compilation and finalization.
·
Acted as consultant to the NRC Equipment
Qualification Branch for audits of commercial reactors. This involved checking for compliance with
requirements for proper testing and analysis of equipment that is used for safe
shutdown and post-accident monitoring and control.
Risk/Safety Analysis
·
Provided Consulting Services for a FMEA to the
designers of the melter used at the
RPP-WTP.
·
Responsible for all aspects of risk analysis
including FMEA, Initiating Event Development, Data Analysis, System Modeling
for numerous Commercial Operating Reactor Facilities and DOE/DOD Sites.
·
Investigated the application of Swiss-developed
risk-based explosives siting criteria to US Department of Defense
facilities, where a deterministic siting criteria is used. This involved gaining an understanding of the
Swiss experience in implementing risk-based siting, application of their
criteria to selected United States Air Force siting problems, and providing a
report on the feasibility of converting the United States military to
risk-based siting criteria.
·
Retrieved event data from the Occurrence
Reporting and Processing System for Lessons-Learned Seminars on hoisting and
rigging and chlorine systems. The task
involved down-loading occurrence reports, analyzing them for trends and root
causes, and presenting the results at seminars sponsored by EH‑30.
·
Involved in the performance of PRAs for the dual
unit sites of a large multi-station utility.
He performed as the lead technical analyst for systems analysis and
performed the support model development.
These PRAs were performed using the support-state/ front-line-system
event tree techniques utilizing dependent fault trees. Provided training to the customer on fault
tree analysis.
·
Responsible for the oversight of portions of the
ATR Program at the INEL. Lead technical
responsibility for the reactor safety and analysis work, including a program to
update the facility SAR and the full scope ATR Probabilistic Safety
Analysis. Held collateral responsibility
for reactor and experiment operations, environmental documentation, facility
modifications, quality assurance, and budget. Had duties associated with the operation of
three critical assemblies.
·
Responsible for the performance of Level I
of the ATR PRA, including accident initiator identification, event and fault
tree construction, external event analysis, failure data development, and
quantification. Also required to provide
input to the project manager for schedule, scope, and budget changes, and to
make presentations to local and headquarters organizations of the Department of
Energy (DOE) and internal review groups.
·
Conducted a demonstration
reliability/vulnerability analysis on selected Hill Air Force Base energy
systems. This led to production studies
at Malmstrom and Robins Air Force Bases.
These studies involved working with highly classified documents and
producing reports.
·
Developed procedures for applying the results of
previously performed PRAs to the inspection programs that the NRC applies to
operating reactors as part of the NRC's PRA Applications Program for Inspection
of Nuclear Power Plants. This project
also included development of a LISP‑based computer program to analyze the
results of Pickard, Lowe, and Garrick, Inc. developed PRAs. A method was also developed for application
of generic insights from PRAs of Westinghouse plants to inspection of
Westinghouse plants without PRAs.
·
Performed system analysis and quantification for
the NRC Accident Sequence Evaluation Program, which involved a majority of the
commercial reactor plants in the U.S.
·
Analyzed data input procedures and database use
for the Nuclear Regulatory Commission (NRC) Sequence Coding and Search System
failure data program.
·
Performed system analysis, including taking the
lead position for system fault tree quantification in support of the second PRA
for the Clinch River Breeder Reactor.
·
Qualified
as operator of the ATR experiment loops.
These loops are operated under pressurized water reactor conditions for
the testing of materials and fuels that are used in the U.S. Navy nuclear power
program.
Naval Operations
·
Operated and maintained reactor power plants on
surface ships and at the Naval Reactors Facility (NRF) prototype. Engineering Watch Supervisor, Crew Leading
Electrician, and Instructor at NRF.
·
Safety and Risk Analysis Consulting Associate
2000-Present
·
Senior Research Engineer, 1/94 - 2001, Battelle
Memorial Institute, Pacific Northwest National Laboratory, Richland, WA
·
Consultant / Analyst, 1/91 - 1/94, Tenera, Idaho
Falls, ID
·
Industrial Specialist, 11/89 - 1/91, Department
of Energy, Idaho Operations Office, Idaho Falls, ID
·
Engineer, 1/80 - 11/89, EG&G Idaho, Idaho National
Engineering Laboratory, Idaho Falls,
ID
·
Electrician's Mate First Class, 1/72 - 12/79,
U.S. Navy, various commands including Naval Reactors Facility, Idaho Falls, ID
et
al, 1981, "Audit of the Environmental Qualification of Safety‑Related
Electrical Equipment at the LaSalle County Station (Unit 1)", EGG‑EA‑5514.
et
al, 1981, "Audit of the Environmental Qualification of Safety‑Related
Electrical Equipment at the Virgil C. Summer Nuclear Station", EGG‑EA‑5537.
et
al, 1981, "Audit of the Environmental Qualification of Safety‑Related
Electrical Equipment at the Enrico Fermi Atomic Power Plant, Unit 2", EGG‑EA‑5534.
et
al, 1981, "Audit of the Environmental Qualification of Safety‑Related
Electrical Equipment at General Electrical Company, San Jose, CA", EGG‑EA‑5620.
et
al, 1981, "Audit of Pacific Gas and Electric's Documentation Concerning
Environmental Qualification of Safety‑Related Electrical Equipment Per
NUREG‑0588 for the Diablo Canyon Nuclear Plants", EGG‑EA‑5637.
et
al, 1982, "Reaudit of the Environmental Qualification of Safety‑Related
Electrical Equipment at the Enrico Fermi Atomic Power Plant, Unit 2", EGG‑EA‑5796.
et
al, 1983, "Clinch River Breeder Reactor Plant Probabilistic Risk
Assessment ‑ Phase I", EGG‑EA‑6162.
et
al, 1983, "Sequence Coding and Search System Technical Audit", EGG‑EA‑6221.
et
al, 1985, "Event Tree Analysis Using Artificial Intelligence
Techniques", presented at the American Nuclear Society International
Topical Meeting on Computer Applications for Nuclear Power Plant Operation and
Control, Pasco, Washington.
et
al, 1985, "Reviewing the Development of an Artificial Intelligence Based
Risk Program", presented at the American Nuclear Society Winter Meeting, San Francisco, California.
et
al, 1986, "PRA Applications Program for Inspection at Seabrook Station",
EGG‑EA‑7194.
et
al, 1986, "PRA Applications Program for Inspection at the Zion Nuclear
Power Station", EGG‑EA‑7304.
et
al, 1986, "Pilot PRA Applications Program for Inspection at Indian
Point 2", EGG‑EA‑7136, Rev. 1.
et
al, 1986, "Application of Generic PRA‑Based Inspection Guidelines to
Haddam Neck Station", EGG‑EA‑7491.
et
al, 1986, "A Demonstration of Energy Vulnerability Assessment Using
Reliability Techniques", EGG‑EA‑7452.
et
al, 1987, "Application of Generic PRA Insights to NRC Inspection",
presented at the Probabilistic Safety Assessment and Risk Management PSA '87, Zurich, Switzerland.
et
al, 1989, "Interim Level 1 Advanced Test Reactor Probabilistic Risk
Assessment", EGG-PRP-8039.
et
al, 1992, "Commonwealth Edison Company Dresden Nuclear Power Plant Units 2 and 3
Individual Plant Examination", Individual Plant Examination Partnership.
et
al, 1993, "Commonwealth Edison Company Quad Cities Nuclear Power Plant Units
1 and 2 Individual Plant Examination", Individual Plant Examination
Partnership.
