Regulatory Guide: Issuance, Availability, 6794-6795 [E6-1774]
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6794
Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Notices
NATIONAL SCIENCE FOUNDATION
Notice of Intent To Extend an
Information Collection
National Science Foundation.
Notice and request for
comments.
AGENCY:
ACTION:
In compliance with the
requirement of Section 3506(c)(2)(A) of
the Paperwork Reduction Act of 1995
for opportunity for public comment on
proposed data collection projects, the
National Science Foundation (NSF) will
publish periodic summaries of proposed
projects.
Comments are invited on (a) Whether
the proposed collection of information
is necessary for the proper performance
of the functions of the agency, including
whether the information shall have
practical utility; (b) the accuracy of the
agency’s estimate of the burden of the
proposed collection of information; (c)
ways to enhance the quality, utility, and
clarity of the information to be
collected; and (d) ways to minimize the
burden of the collection of information
on respondents, including through the
use of automated collection techniques
or other forms of information
technology.
SUMMARY:
Written comments on this notice
must be received by April 10, 2006, to
be assured of consideration. Comments
received after that date will be
considered to the extent practicable.
FOR FURTHER INFORMATION CONTACT:
Suzanne H. Plimpton, Reports Clearance
Officer, National Science Foundation,
4201 Wilson Boulevard, Suite 295,
Arlington, Virginia 22230; telephone
(703) 292–7556; or send e-mail to
splimpto@nsf.gov. Individuals who use
a telecommunications device for the
deaf (TDD) may call the Federal
Information Relay Service (FIRS) at 1–
800–877–8339 between 9 a.m. and 9
p.m., Eastern time, Monday through
Friday. You also may obtain a copy of
the data collection instrument and
instructions from Ms. Plimpton.
SUPPLEMENTARY INFORMATION:
Title of Collection: Request for
Proposals.
OMB Approval Number: 3145–0080.
Expiration Date of Approval: May 31,
2006.
Type of Request: Intent to seek
approval to extend an information
collection for three years.
Proposed Project: The Federal
Acquisition Regulations (FAR) Subpart
15.2—‘‘Solicitation and Receipt of
Proposals and Information’’ prescribes
policies and procedures for preparing
and issuing Requests for Proposals. The
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DATES:
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FAR System has been developed in
accordance with the requirement of the
Office of Federal Procurement Policy
Act of 1974, as amended. The NSF Act
of 1950, as amended, 42 U.S.C. 1870,
Section II, states that NSF has the
authority to:
(c) Enter into contracts or other
arrangements, or modifications thereof, for
the carrying on, by organizations or
individuals in the United States and foreign
countries, including other government
agencies of the United States and of foreign
countries, of such scientific or engineering
activities as the Foundation deems necessary
to carry out the purposes of this Act, and, at
the request of the Secretary of Defense,
specific scientific or engineering activities in
connection with matters relating to
international cooperation or national
security, and, when deemed appropriate by
the Foundation, such contracts or other
arrangements or modifications thereof, may
be entered into without legal consideration,
without performance or other bonds and
without regard to section 5 of title 41, U.S.C.
Use of the Information: Request for
Proposals (RFP) is used to competitively
solicit proposals in response to NSF
need for services. Impact will be on
those individuals or organizations who
elect to submit proposals in response to
the RFP. Information gathered will be
evaluated in light of NSF procurement
requirements to determine who will be
awarded a contract.
Estimate of Burden: The Foundation
estimates that, on average, 558 hours per
respondent will be required to complete
the RFP.
Respondents: Individuals; business or
other for-profit; not-for-profit
institutions; Federal government; state,
local, or tribal governments.
Estimated Number of Responses: 75.
Estimated Total Annual Burden on
Respondents: 41,850 hours.
Dated: February 3, 2006.
Suzanne H. Plimpton,
Reports Clearance Officer, National Science
Foundation.
[FR Doc. 06–1192 Filed 2–8–06; 8:45 am]
BILLING CODE 7555–01–M
NUCLEAR REGULATORY
COMMISSION
Regulatory Guide: Issuance,
Availability
The U.S. Nuclear Regulatory
Commission (NRC) has issued a new
guide in the agency’s Regulatory Guide
Series. This series has been developed
to describe and make available to the
public such information as methods that
are acceptable to the NRC staff for
implementing specific parts of the
NRC’s regulations, techniques that the
PO 00000
Frm 00048
Fmt 4703
Sfmt 4703
staff uses in evaluating specific
problems or postulated accidents, and
data that the staff needs in its review of
applications for permits and licenses.
Regulatory Guide 1.203, ‘‘Transient
and Accident Analysis Methods,’’
provides guidance for NRC licensees
and applicants to use in developing and
assessing evaluation models that may be
used to analyze transient and accident
behavior that is within the design basis
of a nuclear power plant. Evaluation
models that the NRC has previously
approved will remain acceptable and
need not be revised to conform with the
guidance given in this regulatory guide.
Chapter 15 of the NRC’s ‘‘Standard
Review Plan (SRP) for the Review of
Safety Analysis Reports for Nuclear
Power Plants’’ (NUREG–0800) and the
‘‘Standard Format and Content of Safety
Analysis Reports for Nuclear Power
Plants’’ (Regulatory Guide 1.70) describe
a subset of the transient and accident
events that must be considered in the
safety analyses required by Title 10, part
50, of the Code of Federal Regulations
(10 CFR part 50), ‘‘Domestic Licensing
of Production and Utilization
Facilities,’’ section 50.34, ‘‘Contents of
Applications; Technical Information’’
(10 CFR 50.34). In particular, 10 CFR
50.34 specifies the following
requirements regarding applications for
construction permits and/or licenses to
operate a facility:
(1) Safety analysis reports must
analyze the design and performance of
structures, systems, and components,
and their adequacy for the prevention of
accidents and mitigation of the
consequences of accidents.
(2) Analysis and evaluation of
emergency core cooling system (ECCS)
cooling performance following
postulated loss-of-coolant accidents
(LOCAs) must be performed in
accordance with the requirements of 10
CFR 50.46.
(3) The technical specifications for the
facility must be based on the safety
analysis and prepared in accordance
with the requirements of 10 CFR 50.36.
An additional benefit is that
evaluation models that are developed
using the guidelines provided in
Regulatory Guide 1.203 will provide a
more reliable framework for riskinformed regulation and a basis for
estimating the uncertainty in
understanding transient and accident
behavior.
In addition, the NRC is issuing section
15.0.2 of the SRP, which covers the
same subject material as Regulatory
Guide 1.203, and is intended to
complement the guide. Specifically,
section 15.0.2 provides guidance to NRC
reviewers of transient and accident
E:\FR\FM\09FEN1.SGM
09FEN1
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Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Notices
analysis methods, while Regulatory
Guide 1.203 provides practices and
principles for the benefit of method
developers. Chapter 15 of the SRP
recommends using approved evaluation
models or codes for the analysis of most
identified events. The SRP also suggests
that evaluation model reviews should be
initiated whenever an approved model
does not exist for a specified plant
event. If the applicant or licensee
proposes to use an unapproved model,
an evaluation model review should be
initiated.
The NRC previously solicited public
comment on this guide by publishing a
Federal Register notice (65 FR 77934)
concerning Draft Regulatory Guide DG–
1096 on December 13, 2000, followed by
a Federal Register notice (68 FR 4524)
concerning Draft Regulatory Guide DG–
1120 on January 29, 2003. Following the
closure of the latest public comment
period on March 24, 2003, the staff
considered all stakeholder comments in
the course of preparing the new
Regulatory Guide 1.203.
The NRC staff encourages and
welcomes comments and suggestions in
connection with improvements to
published regulatory guides, as well as
items for inclusion in regulatory guides
that are currently being developed. You
may submit comments by any of the
following methods.
Mail comments to: Rules and
Directives Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
Hand-deliver comments to: Rules and
Directives Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, 11555 Rockville Pike,
Rockville, Maryland 20852, between
7:30 a.m. and 4:15 p.m. on Federal
workdays.
Fax comments to: Rules and
Directives Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, at (301) 415–5144.
Requests for technical information
about Regulatory Guide 1.203 may be
directed to Shawn O. Marshall at (301)
415–5861 or via e-mail to SOM@nrc.gov.
Regulatory guides are available for
inspection or downloading through the
NRC’s public Web site in the Regulatory
Guides document collection of the
NRC’s Electronic Reading Room at
https://www.nrc.gov/reading-rm/doccollections. Electronic copies of
Regulatory Guide 1.203 and SRP section
15.0.2 are also available in the NRC’s
Agencywide Documents Access and
Management System (ADAMS) at https://
www.nrc.gov/reading-rm/adams.html,
under Accession Nos. ML053500170
and ML053550265, respectively.
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17:24 Feb 08, 2006
Jkt 208001
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR), which is
located at 11555 Rockville Pike,
Rockville, Maryland; the PDR’s mailing
address is USNRC PDR, Washington, DC
20555–0001. The PDR can also be
reached by telephone at (301) 415–4737
or (800) 397–4205, by fax at (301) 415–
3548, and by email to PDR@nrc.gov.
Requests for single copies of draft or
final guides (which may be reproduced)
or for placement on an automatic
distribution list for single copies of
future draft guides in specific divisions
should be made in writing to the U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, Attention:
Reproduction and Distribution Services
Section; by e-mail to
DISTRIBUTION@nrc.gov; or by fax to
(301) 415–2289. Telephone requests
cannot be accommodated.
Regulatory guides are not
copyrighted, and Commission approval
is not required to reproduce them.
(5 U.S.C. 552(a))
Dated at Rockville, Maryland, this 29th day
of December, 2005.
For the U.S. Nuclear Regulatory
Commission.
James T. Wiggins,
Deputy Director, Office of Nuclear Regulatory
Research.
[FR Doc. E6–1774 Filed 2–8–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Regulatory Guide: Issuance,
Availability
The U.S. Nuclear Regulatory
Commission (NRC) has issued a new
guide in the agency’s Regulatory Guide
Series. This series has been developed
to describe and make available to the
public such information as methods that
are acceptable to the NRC staff for
implementing specific parts of the
NRC’s regulations, techniques that the
staff uses in evaluating specific
problems or postulated accidents, and
data that the staff needs in its review of
applications for permits and licenses.
Regulatory Guide 1.201, ‘‘Guidelines
for Categorizing Structures, Systems,
and Components in Nuclear Power
Plants According to Their Safety
Significance,’’ which is being issued for
trial use, provides guidance for use in
developing and assessing evaluation
models for accident and transient
analyses. An additional benefit is that
evaluation models that are developed
using these guidelines will provide a
more reliable framework for risk-
PO 00000
Frm 00049
Fmt 4703
Sfmt 4703
6795
informed regulation and a basis for
estimating the uncertainty in
understanding transient and accident
behavior.
The NRC has promulgated regulations
to permit power reactor licensees and
license applicants to implement an
alternative regulatory framework with
respect to ‘‘special treatment,’’ where
special treatment refers to those
requirements that provide increased
assurance beyond normal industrial
practices that structures, systems, and
components (SSCs) perform their
design-basis functions. Under this
framework, licensees using a riskinformed process for categorizing SSCs
according to their safety significance
can remove SSCs of low safety
significance from the scope of certain
identified special treatment
requirements.
The genesis of this framework stems
from Option 2 of SECY–98–300,
‘‘Options for Risk-Informed Revisions to
10 CFR part 50, ‘Domestic Licensing of
Production and Utilization Facilities’,’’
dated December 23, 1998.1 In that
Commission paper, the NRC staff
recommended developing risk-informed
approaches to the application of special
treatment requirements to reduce
unnecessary regulatory burden related
to SSCs of low safety significance by
removing such SSCs from the scope of
special treatment requirements. The
Commission subsequently approved the
NRC staff’s rulemaking plan and
issuance of an Advanced Notice of
Proposed Rulemaking (ANPR) as
outlined in SECY–99–256, ‘‘Rulemaking
Plan for Risk-Informing Special
Treatment Requirements,’’ dated
October 29, 1999.
The Commission published the ANPR
in the Federal Register (65 FR 11488) on
March 3, 2000, and subsequently
published a proposed rule for public
comment (68 FR 26511) on May 16,
2003. Then, on November 22, 2004, the
Commission adopted a new section,
referred to as § 50.69, within Title 10,
part 50, of the Code of Federal
Regulations, on risk-informed
categorization and treatment of SSCs for
nuclear power plants (69 FR 68008).
This trial regulatory guide describes a
method that the NRC staff considers
acceptable for use in complying with
the Commission’s requirements in
§ 50.69 with respect to the
1 Commission papers cited in this notice are
available through the NRC’s public Web site at
https://www.nrc.gov/reading-rm/doc-collections/
commission/secys/, and the related Federal
Register notices are available through the Federal
Register Web site sponsored by the Government
Printing Office (GPO) at https://www.gpoaccess.gov/
fr/.
E:\FR\FM\09FEN1.SGM
09FEN1
Agencies
[Federal Register Volume 71, Number 27 (Thursday, February 9, 2006)]
[Notices]
[Pages 6794-6795]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-1774]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Regulatory Guide: Issuance, Availability
The U.S. Nuclear Regulatory Commission (NRC) has issued a new guide
in the agency's Regulatory Guide Series. This series has been developed
to describe and make available to the public such information as
methods that are acceptable to the NRC staff for implementing specific
parts of the NRC's regulations, techniques that the staff uses in
evaluating specific problems or postulated accidents, and data that the
staff needs in its review of applications for permits and licenses.
Regulatory Guide 1.203, ``Transient and Accident Analysis
Methods,'' provides guidance for NRC licensees and applicants to use in
developing and assessing evaluation models that may be used to analyze
transient and accident behavior that is within the design basis of a
nuclear power plant. Evaluation models that the NRC has previously
approved will remain acceptable and need not be revised to conform with
the guidance given in this regulatory guide.
Chapter 15 of the NRC's ``Standard Review Plan (SRP) for the Review
of Safety Analysis Reports for Nuclear Power Plants'' (NUREG-0800) and
the ``Standard Format and Content of Safety Analysis Reports for
Nuclear Power Plants'' (Regulatory Guide 1.70) describe a subset of the
transient and accident events that must be considered in the safety
analyses required by Title 10, part 50, of the Code of Federal
Regulations (10 CFR part 50), ``Domestic Licensing of Production and
Utilization Facilities,'' section 50.34, ``Contents of Applications;
Technical Information'' (10 CFR 50.34). In particular, 10 CFR 50.34
specifies the following requirements regarding applications for
construction permits and/or licenses to operate a facility:
(1) Safety analysis reports must analyze the design and performance
of structures, systems, and components, and their adequacy for the
prevention of accidents and mitigation of the consequences of
accidents.
(2) Analysis and evaluation of emergency core cooling system (ECCS)
cooling performance following postulated loss-of-coolant accidents
(LOCAs) must be performed in accordance with the requirements of 10 CFR
50.46.
(3) The technical specifications for the facility must be based on
the safety analysis and prepared in accordance with the requirements of
10 CFR 50.36.
An additional benefit is that evaluation models that are developed
using the guidelines provided in Regulatory Guide 1.203 will provide a
more reliable framework for risk-informed regulation and a basis for
estimating the uncertainty in understanding transient and accident
behavior.
In addition, the NRC is issuing section 15.0.2 of the SRP, which
covers the same subject material as Regulatory Guide 1.203, and is
intended to complement the guide. Specifically, section 15.0.2 provides
guidance to NRC reviewers of transient and accident
[[Page 6795]]
analysis methods, while Regulatory Guide 1.203 provides practices and
principles for the benefit of method developers. Chapter 15 of the SRP
recommends using approved evaluation models or codes for the analysis
of most identified events. The SRP also suggests that evaluation model
reviews should be initiated whenever an approved model does not exist
for a specified plant event. If the applicant or licensee proposes to
use an unapproved model, an evaluation model review should be
initiated.
The NRC previously solicited public comment on this guide by
publishing a Federal Register notice (65 FR 77934) concerning Draft
Regulatory Guide DG-1096 on December 13, 2000, followed by a Federal
Register notice (68 FR 4524) concerning Draft Regulatory Guide DG-1120
on January 29, 2003. Following the closure of the latest public comment
period on March 24, 2003, the staff considered all stakeholder comments
in the course of preparing the new Regulatory Guide 1.203.
The NRC staff encourages and welcomes comments and suggestions in
connection with improvements to published regulatory guides, as well as
items for inclusion in regulatory guides that are currently being
developed. You may submit comments by any of the following methods.
Mail comments to: Rules and Directives Branch, Office of
Administration, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
Hand-deliver comments to: Rules and Directives Branch, Office of
Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville
Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on
Federal workdays.
Fax comments to: Rules and Directives Branch, Office of
Administration, U.S. Nuclear Regulatory Commission, at (301) 415-5144.
Requests for technical information about Regulatory Guide 1.203 may
be directed to Shawn O. Marshall at (301) 415-5861 or via e-mail to
SOM@nrc.gov.
Regulatory guides are available for inspection or downloading
through the NRC's public Web site in the Regulatory Guides document
collection of the NRC's Electronic Reading Room at https://www.nrc.gov/
reading-rm/doc-collections. Electronic copies of Regulatory Guide
1.203 and SRP section 15.0.2 are also available in the NRC's Agencywide
Documents Access and Management System (ADAMS) at https://www.nrc.gov/
reading-rm/adams.html, under Accession Nos. ML053500170 and
ML053550265, respectively.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR), which is located at 11555 Rockville
Pike, Rockville, Maryland; the PDR's mailing address is USNRC PDR,
Washington, DC 20555-0001. The PDR can also be reached by telephone at
(301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548, and by
email to PDR@nrc.gov. Requests for single copies of draft or final
guides (which may be reproduced) or for placement on an automatic
distribution list for single copies of future draft guides in specific
divisions should be made in writing to the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, Attention: Reproduction and
Distribution Services Section; by e-mail to DISTRIBUTION@nrc.gov; or by
fax to (301) 415-2289. Telephone requests cannot be accommodated.
Regulatory guides are not copyrighted, and Commission approval is
not required to reproduce them.
(5 U.S.C. 552(a))
Dated at Rockville, Maryland, this 29th day of December, 2005.
For the U.S. Nuclear Regulatory Commission.
James T. Wiggins,
Deputy Director, Office of Nuclear Regulatory Research.
[FR Doc. E6-1774 Filed 2-8-06; 8:45 am]
BILLING CODE 7590-01-P