| The Nuclear Regulatory Commission
is seeking comments on its proposed agenda for the Nuclear Safety Research
Conference, which will be held October 28-30 at the Marriott at Metro Center,
located at 775 12th Street, N.W. in Washington, D.C. Formerly known as "The
Water Reactor Safety Meeting," the conference is designed to promote dialogue
with stakeholders on research matters and gather feedback for future agency
regulatory decisions.
The conference is an international regulatory gathering attended by researchers,
regulators and utility representatives from the United States and some 20
other countries. It will provide participants with the opportunity to interact
with NRC officials and colleagues to better understand the agency's research
programs and its safety priorities.
The complete proposed agenda is attached. Comments should be forwarded
by July 15 via e-mail to Sandra Nesmith, at srn@nrc.gov.
|
PRELIMINARY AGENDA
Nuclear Safety Research Conference (NSRC)
October 28-30, 2002
Marriott at Metro Center
(775 12th St. NW, Washington DC)
|
| 8:30-8:45am |
Opening Remarks |
| 8:45-9:30am |
Keynote Speaker |
| 9:30 - 11:30am |
Panel Discussion - Advanced Reactors
Objective: This panel will discuss the regulatory research needed
to support the licensing of advanced reactor designs and focus on the kind
of research that is needed to resolve technical/policy issues.
Potential panel members to include:Representatives
from DOE, Industry, University, public interest groups, and NRC.
|
| 11:30 - 1:00pm |
LUNCH
|
| 1:00 - 5:00pm |
Degradation of Reactor Coolant Pressure Boundary
Materials
Objective:To describe the results of research
addressing the response of reactor coolant pressure boundary materials
to active degradation mechanisms and mitigation/repair methodologies.
Potential topics for presentation include:
- Discussion of PWSCC, Alloy 600, and welds
|
Advanced Reactors Session
Objective: To present specific work or planned work on gas cooled
reactors and present DOE's envision for Generation IV reactors.
Potential topics for presentation include:
- Test matrix for TRISO fuel
- Applications of graphite technology to advanced reactors
- Generation IV roadmap
- GRSAC code as a regulatory tool
|
|
Tuesday, October 29, 2002
|
| 8:30 - 9:30am |
Plenary - NRC Chairman Speech |
| 9:45 - 11:45am |
Fuels Session
Objective: To describe recent work on the technical basis for
embrittlement criteria and evaluation models that are applicable at high
burnup for loss-of-coolant accident (LOCA) analysis and for establishing
optional performance-based criteria in 10 CFR 50.45
Potential topics for presentation include:
- Testing of high burnup BWR fuel under simulated LOCA conditions
- Measurement of oxidation kinetics of cladding from high burnup fuel
- Testing for ductility in cladding subjected to LOCA conditions
- - Analysis of high burnup fuel behavior under LOCA conditions
|
Formal Decision Methods and Nuclear
Safety Research
Objective: To describe research activities for developing the
technical basis and enhancing the transparency and objectivity of decision-making
in the regulatory environment.
Potential topics for presentation include:
- The formal decision making framework
- Probabilistic risk analysis: a component of formal decision-making
- Research activities in the field of regulatory decision-making
- Stakeholder input to the decision-making process
|
| 11:45 - 1:15pm |
LUNCH |
| 1:15 - 5:00pm |
Dry Cask Storage and Transportation of Spent Nuclear
Fuel Session
Objective: To communicate recent accomplishments
and future plans to assess key safety issues related to spent fuel transportation
and storage in dry casks.
Potential topics for presentation include:
- Determination of the performance of dry casks during transportation
- Risk Assessment of on-site dry casks
- Assessment of structural integrity of on-site storage casks
|
Fuels Session
Objective: To describe recent work on the technical basis for
fuel enthalpy criteria that are applicable at high burnup for reactivity-initiated
accident (RIA) analysis and for modifying Regulatory Guide 1.77.
Potential topics for presentation include:
- Testing of high burnup fuel under simulated RIA conditions
- Measurement of cladding-to-coolant heat during transients
- Measurement of cladding mechanical properties applicable to RIA conditions
- Analysis of high-burnup fuel behavior under RIA conditions
|
|
Wednesday, October 30, 2002
|
| 8:30-9:15am |
Plenary - Commissioner Speech |
| 9:30-11:30am |
Panel Discussion - Risk Informed Initiatives
Objective:This panel will communicate recent
improvements on how NRC uses risk information in regulatory decision making
and how work in the Office of Nuclear Regulatory Research supports such
uses.
Potential panel members include: Representatives
of industry, EPRI, international organizations, and NRC. |
| 11:30 - 1:00pm |
LUNCH
|
| 1:00 - 3:00pm |
Clearance Session (Session A)
Objective: To discuss the status on the development
of the technical basis for control of slightly contaminated materials.
Potential topics for presentations include:
- Surveys of volumetric contamination and difficult geometries
- Revision of NUREG-1640 (individual doses)
- Follow-on work to address collective doses
|
PRA Session (Methods/Analysis, and Operational
Experience)
Objective: To communicate recent advances in risk analysis methods
as well as recent advances in using operational data in agency regulatory
activities. Potential topics for presentation include:
- Fire risk analysis
- Human reliability analysis
- Assessment of uncertainties
- PRA standards
- Standardized plant analysis risk (SPAR) models
- Risk-based performance indicators
|
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