NRC NEWS

 U.S. NUCLEAR REGULATORY COMMISSION 

 Office of Public Affairs Telephone: 301/415-8200

 Washington, DC 20555-0001 E-mail: opa@nrc.gov 

 Web Site: www.nrc.gov

No. 02-077 June 26, 2002

NRC SEEKS COMMENTS ON PROPOSED AGENDA

FOR ANNUAL NUCLEAR SAFETY RESEARCH CONFERENCE IN OCTOBER

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 email 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)

Monday, October 28, 2002

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 decisionmaking 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 reactivityinitiated 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

3:15pm CLOSING REMARKS