[Federal Register Volume 74, Number 48 (Friday, March 13, 2009)]
[Notices]
[Page 10969]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E9-5450]
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NUCLEAR REGULATORY COMMISSION
Advisory Committee on Reactor Safeguards, Meeting of the ACRS
Subcommittee on Reliability and Probabilistic Risk Assessment; Notice
of Meeting
The ACRS Subcommittee on Reliability and Probabilistic Risk
Assessment (PRA) will hold a meeting on March 27, 2009, Room T-2-B3,
11545 Rockville Pike, Rockville, Maryland.
The entire meeting will be open to public attendance.
The agenda for the subject meeting shall be as follows:
Friday, March 27, 2009--1 p.m. until the conclusion of business.
The Subcommittee will review example uses of the guidance on
performance of sensitivity and uncertainty analyses described in NUREG-
1855. The Subcommittee will hear presentations by and hold discussions
with representatives of the NRC staff. The Subcommittee will gather
information, analyze relevant issues and facts, and formulate proposed
positions and actions, as appropriate, for deliberation by the full
Committee. Members of the public desiring to provide oral statements
and/or written comments should notify the Designated Federal Official,
Harold VanderMolen (Telephone: 301-415-6236) 5 days prior to the
meeting, if possible, so that appropriate arrangements can be made.
Electronic recordings will be permitted only during those portions of
the meeting that are open to the public. Detailed procedures for the
conduct of and participation in ACRS meetings were published in the
Federal Register on October 6, 2008, (73FR 58268-58269).
Further information regarding this meeting can be obtained by
contacting the Designated Federal Official between 8:30 a.m. and 4:30
p.m. (ET). Persons planning to attend this meeting are urged to contact
the above named individual at least two working days prior to the
meeting to be advised of any potential changes to the agenda.
Dated: March 6, 2009.
Cayetano Santos,
Chief, Reactor Safety Branch A, Advisory Committee on Reactor
Safeguards.
[FR Doc. E9-5450 Filed 3-12-09; 8:45 am]
BILLING CODE 7590-01-P