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> July 18, 2002
July 18, 2002
Dr. William D. Travers
Executive Director for Operations
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555-0001
Dear Dr. Travers:
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SUBJECT: |
DRAFT ADVANCED REACTOR RESEARCH PLAN
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During the 494th meeting of the Advisory Committee on Reactor Safeguards,
July 10-12, 2002, and a meeting of our Subcommittee on Future Plant Designs
on July 8, 2002, we were briefed by representatives of the NRC's Office
of Nuclear Regulatory Research (RES) on the subject Plan. We also had
the benefit of the document referenced.
The draft Advanced Reactor Research Plan appears to us to be a very competent
effort by the staff. It is comprehensive and reflects a high level of
understanding of the issues, existing state of the art, and past and ongoing
research results and activities. We commend the RES staff on its effort
to date. The Plan is not yet complete in the sense that it does not establish
resources, schedules, and milestones. Nevertheless, we believe that addressing
the research needs already identified in the Plan is very important.
COMMENTS
- We agree that research on High Temperature Gas Cooled Reactors (HTGRs)
should continue. However, given the current uncertain status of the
Pebble Bed Modular Reactor (PBMR), the research for HTGRs should focus
on generic issues and the Gas Turbine-Modular Helium Reactor (GT-MHR)
concept.
- We consider the development of fission product release models for
TRISO fuels to be the key research need for the gas-cooled reactor concepts.
All the current models for fission product release in the MELCOR computer
code are empirical and based on data obtained from light water reactor
(LWR) fuel at burnup levels less than 45 GWd/t. To extend these models
to HTGRs will require research on fission product release from highly
irradiated HTGR fuel. Even the form of the empirical models (diffusive
in nature) may not be appropriate to TRISO fuel for which the release
of fission products is primarily related to the failure rate of the
coatings, which is not well-described by a diffusive-like correlation.
- A viable research plan can be developed in the absence of a well-defined
framework for risk-informed regulations. However, such a framework can
help prioritize the research and is important for other reasons. The
work on the framework should be given higher priority.
- Plans should be developed for experiments to investigate degradation
and fission product release characteristics of the advanced LWR's core
with very high-burnup fuel [particularly International Reactor Innovative
and Secure (IRIS) design].
- A risk-informed approach for selecting design-basis events and choosing
acceptance criteria for the new designs needs to be developed.
- The use of Phenomena Identification and Ranking Table (PIRT) is an
essential ingredient of the Plan and should be developed early in the
process. Because we have doubts that a "super-PIRT" that encompasses
the entire program would be effective, the PIRTs should be focused on
specific research areas.
- Consideration should be given to research to determine whether the
buildup and characteristics of radioactivity in the coolant system during
the operating phase of the HTGRs could be used to infer whether the
as-installed fuel quality meets the required (licensing-basis) quality.
- The Plan should include an element to maintain cognizance of the international
near-term deployment and GEN IV concepts, with anticipation that research
eventually may be needed to address issues associated with technology
concepts that are significantly different than those of the Plan's focus.
- If in-vessel retention via external flooding of the reactor vessel
is anticipated as an accident management strategy for AP1000 (and perhaps
IRIS), we believe this reopens the need for additional consideration
of fuel coolant interactions (steam explosions). The state of the art
for fuel coolant interactions is not yet sufficiently advanced to predict
the occurrence and energetics of steam explosions.
- Because there is a general need for large-scale integral testing of
new concepts, the staff should evaluate the utility of the proposed
concept of "licensing by test."
Additional comments by ACRS Members Dana A. Powers, Stephen L. Rosen,
and Graham B. Wallis are provided below.
Sincerely,
/RA/
George E. Apostolakis
Chairman
Additional Comments by ACRS Members Dana A. Powers, Stephen L. Rosen,
and Graham B. Wallis
Design-basis accidents are prominent features of the regulatory process
for existing reactors. The design-basis accident concept, which originated
in the 1950s, was an important element of reactor safety analysis in an
era when comprehensive, integrated analyses involving wide ranges of accident
initiators and the possibility of multiple systems failures were not practical
undertakings. It can be argued that design-basis accidents have served
the safety regulation of the current generation of nuclear power plants
well. It must also be acknowledged that the accident at Three Mile Island
revealed deficiencies of the design-basis accident concept. Design-basis
accidents divert safety focus toward stylized accidents that, by definition,
have exceptionally low probabilities at the expense of ensuring plants
have capabilities of coping with more likely events.
The conduct of comprehensive, integrated plant analyses is now well-developed
and, indeed, such analyses are essential features of the regulatory process
for advanced reactors. These analyses supplant the need for design-basis
accidents in the regulatory process for advanced reactors. Specialized
attention to a few, low probability accidents does not add to plant safety
if integrated, comprehensive accident analyses are done well. Design-basis
accidents do create unnecessary burdens for both licensees and regulators.
Design-basis accidents, then, should not be considered in the Advanced
Reactor Research Plan.
Reference:
U. S. Nuclear Regulatory Commission, Advanced Reactor Research Plan (Draft),
Revision 1, Office of Nuclear Regulatory Research, June 2002.
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