GRADED QUALITY ASSURANCE (GQA)Led the review and wrote the 1997 safety evaluation (SE) for the GQA pilot application, the first risk-informed (RI) license amendment. That SE first used the generic phrase, “the quality of the PRA is sufficient to support the requested application.” INSERVICE INSPECTION (ISI)Led the reviews and wrote the SEs for all RI-ISI methods. NRC accepted a simple method that bins welds and a complex method that simulates flaw lifetimes. The simple method became part of the ASME code. The complex method was used to double the inspection intervals of PWR reactor vessels and vessel nozzle welds and coolant pump flywheels, and to support the 50.61a PTS rule.TECHNICAL SPECIFICATIONSTSTF-505 replaces some fixed TechSpec completion times (CTs) with times calculated from the risk of the plant when the CT is entered. As a lead reviewer on the CT pilots, I noted that the application was effectively replacing design basis success criteria with PRA success criteria. The NRC further investigated the issue and decided not to permit this replacement. TSTF-505 Rev. 1 was suspended and replaced with Rev. 2 . FIRE PROTECTION In 2004, 50.48(c) on risk-informed fire protection was issued. The rule requires that the PRA shall be acceptable. The pilot and subsequent reviews corrected many methods that the staff did not find acceptable. I was involved as lead or support in the pilots and most of the LAR reviews.RULE-MAKINGI supported the 2004, 50.69 rule that reduced special treatment requirements, and the 2010, 50.61a rule that provided alternative acceptable reactor flaw distributions. In 2012 NRC issued NUREG-2150, “A Proposed Risk Management Regulatory Framework.” I was lead PRA contributor to the 2013 SECY 13-0132 that detailed a proposal to implement NUREG-2150. The industry commented that the costs were underestimated and did not support the SECY. In an SRM the Commission stopped further development until a after new policy statement

Developed PRA logic models for the TÜV Norddeutschland’s proposed “living PSA” computer system (SAIS). The system interlinked PRA logic models with existing plant documentation such as P&IDs and system and component information. The system strained the capabilities of the computers and data bases that were readily available in the early 1990s.Summarized Germany’s contribution to the IAEA Safety Series Report No. 106, The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety, May 1992.Converted the assumptions and results of about 20 IPE’s into a standard format and input the information into Brookhaven National Laboratory’s (short-lived) IPE data base.

One of several principal investigators in the safety audit of the low and intermediate level radioactive waste treatment and storage facility in Moll, Belgium.Evaluated and compared computer systems IRRAS, PSAPACK, Super-tree and NUPRA that were being developed to support the performance and use of PRAs.

Performed a variety of PRA method development, review, and application tasks to support Statens kärnkraftinspektion (SKI, Swedish Nuclear Power Inspectorate) investigation of PRA as a safety enhancing tool. Methods used included fire analyses, seismic analyses, common cause failure analysis, uncertainty propagation, and human error analysis.Participated in and edited the final report for the 24 man-year SÄK-1 reliability techniques research project.Supported ASEA-Atom’s PRA for the Forsmark 3 power plant in Sweden.

Reviewed PRA techniques and technical reports used by consulting firms to calculated and report on public risk for the Yankee Rowe and the Seabrook Power plants.Obtain, organized, and used the computer codes and PRA models delivered to Yankee Atomic to investigate safety issues.

Obtained Reactor Operator and Senior Reactor Operating License for MIT's 5MWt Research Reactor in 1979. Participated in all phases of weekly reactor startup and shutdown of the reactor, including supervision as SRO after experience requirements met.

Obtained Reactor operator license in 1978 for UCLA's 100 KWt Research Reactor. Handled startups, console operation, and shutdown of the reactor for scheduled experiments.