Regulatory Guide: Issuance, Availability, 26392-26393 [E6-6747]
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26392
Federal Register / Vol. 71, No. 86 / Thursday, May 4, 2006 / Notices
On
September 2, 2004, the Church filed an
R&PP Act application for 5 acres of
public land to be developed as a church
and related facilities. These related
facilities include a multipurpose
building (a worship center, offices,
classrooms, nursery, kitchen, restrooms,
utility/storage rooms, and a lobby),
sidewalks, landscaped areas, paved
parking areas, and off site
improvements. Additional detailed
information pertaining to this
application, plan of development, and
site plan is in case file N–79030 located
in the BLM Las Vegas Field Office at the
above address. A Notice of Realty
Action was previously published and
the land segregated with a slightly
different legal description on July 28,
2005 (70 FR 43704). The Church
proposes to use the following described
public land for a church and related
facilities:
SUPPLEMENTARY INFORMATION:
mstockstill on PROD1PC68 with NOTICES
Mount Diablo Meridian, Nevada
T. 23 S., R. 61 E.,
Sec. 11, SE1⁄4NE1⁄4NW1⁄4SE1⁄4,
NE1⁄4SE1⁄4NW1⁄4SE1⁄4,
Containing 5 acres, more or less.
Churches are a common applicant
under the ‘‘public purposes’’ provision
of the R&PP Act. The Church is an
Internal Revenue Service registered nonprofit organization and is therefore, a
qualified applicant under the R&PP Act.
The land is not required for any federal
purpose.
The lease/conveyance is consistent
with the Las Vegas Resource
Management Plan, dated October 5,
1998, and would be in the public
interest. The lease/patent, when issued,
will be subject to the provisions of the
R&PP Act and applicable regulations of
the Secretary of the Interior, and will
contain the following reservations to the
United States:
1. A right-of-way thereon for ditches
or canals constructed by the authority of
the United States, Act of August 30,
1890 (43 U.S.C. 945).
2. All minerals shall be reserved to
the United States, together with the
right to prospect for, mine and remove
such deposits from the same under
applicable law and such regulations as
the Secretary of the Interior may
prescribe and will be subject to:
1. An easement in favor of Clark
County for roads, public utilities and
flood control purposes.
2. All valid existing rights
documented on the official public land
records at the time of lease/patent
issuance.
On May 4, 2006, the land described
above will be segregated from all other
forms of appropriation under the public
VerDate Aug<31>2005
15:45 May 03, 2006
Jkt 208001
land laws, including the general mining
laws, except for lease/conveyance under
the R&PP Act, leasing under the mineral
leasing laws, and disposals under the
mineral material disposal laws.
Comments
Classification Comments: Interested
parties may submit comments involving
the suitability of the land for a church
and related facilities. Comments on the
classification are restricted to whether
the land is physically suited for the
proposal, whether the use will
maximize the future use or uses of the
land, whether the use is consistent with
local planning and zoning, or if the use
is consistent with State and Federal
programs.
Application Comments: Interested
parties may submit comments regarding
the specific use proposed in the
application and plan of development,
whether the BLM followed proper
administrative procedures in reaching
the decision, or any other factor not
directly related to the suitability of the
land for R&PP use.
Any adverse comments will be
reviewed by the State Director. In the
absence of any adverse comments, the
classification of the land described in
this notice will become effective July 3,
2006. The lands will not be offered for
lease/conveyance until after the
classification becomes effective.
On May 4, 2006, the R&PP
classification and segregation will
terminate and the following lands will
be opened to the operation of the public
land laws:
Mount Diablo Meridian, Nevada
T. 23 S., R. 61 E.,
Sec. 11, NW1⁄4SE1⁄4NW1⁄4SE1⁄4.
Authority: 43 CFR Part 2741.
Sharon DiPinto,
Assistant Field Manager, Division of Lands,
Las Vegas, NV.
[FR Doc. E6–6716 Filed 5–3–06; 8:45 am]
BILLING CODE 4310–HC–P
NUCLEAR REGULATORY
COMMISSION
Regulatory Guide: Issuance,
Availability
The U.S. Nuclear Regulatory
Commission (NRC) has issued a revision
to an existing 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 NRCs regulations,
techniques that the staff uses in
PO 00000
Frm 00074
Fmt 4703
Sfmt 4703
evaluating specific problems or
postulated accidents, and data that the
staff needs in its review of applications
for permits and licenses.
Revision 1 of 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, describes a method that the
NRC staff considers acceptable for use
in complying with the Commission’s
requirements in Title 10, section 50.69,
of the Code of Federal Regulations
(§ 50.69), with respect to the
categorization of structures, systems,
and components (SSCs) that are
considered in risk-informing special
treatment requirements. This
categorization method uses the process
that the Nuclear Energy Institute (NEI)
described in Revision 0 of its guidance
document NEI 00–04, ‘‘10 CFR 50.69
SSC Categorization Guideline,’’ dated
July 2005.1 Specifically, this process
determines the safety significance of
SSCs and categorizes them into one of
four risk-informed safety class (RISC)
categories.
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 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, 1998.2 In that
Commission paper, the NRC staff
recommended developing risk-informed
approaches to the application of special
treatment requirements to reduce
1 NEI 00–04, ‘‘10 CFR 50.69 SSC Categorization
Guideline,’’ is available through the NRC’s
Agencywide Documents Access and Management
System (ADAMS), https://www.nrc.gov/reading-rm/
adams/ web-based.html, under Accession
#ML052910035.
2 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\04MYN1.SGM
04MYN1
mstockstill on PROD1PC68 with NOTICES
Federal Register / Vol. 71, No. 86 / Thursday, May 4, 2006 / Notices
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).
The NRC issued a draft of this guide,
Draft Regulatory Guide DG–1121, for
public review and comment as part of
the § 50.69 rulemaking package in May
2003. The staff subsequently received
and addressed public comments in
developing the previous revision of this
guide, which the agency published in
January 2006, and has since
incorporated additional stakeholder
comments in preparing the current
revision. However, since this is a new
regulatory approach to categorizing
SSCs, and to ensure that the final
guidance adequately addresses lessons
learned from the initial applications, the
NRC decided to issue this guide for trial
use. Therefore, this trial regulatory
guide does not establish any final staff
positions for purposes of the Backfit
Rule, 10 CFR 50.109, and may continue
to be revised in response to experience
with its use. As such, any changes to
this trial guide prior to staff adoption in
final form will not be considered to be
backfits as defined in 10 CFR
50.109(a)(1). This will ensure that the
final regulatory guide adequately
addresses lessons learned from
regulatory review of pilot and follow-on
applications, and that the guidance is
sufficient to enhance regulatory stability
in the review, approval, and
implementation of probabilistic risk
assessments (PRAs) and their results in
the risk-informed categorization process
required by § 50.69.
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.
VerDate Aug<31>2005
15:45 May 03, 2006
Jkt 208001
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 Revision 1 of Regulatory Guide
1.201 may be directed to Donald G.
Harrison at (301) 415–3587 or via e-mail
to DGH@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
Revision 1 of Regulatory Guide 1.201
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 #ML061090627.
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 e-mail 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.
Authority: 5 U.S.C. 552(a).
Dated at Rockville, Maryland, this 1st day
of May, 2006.
PO 00000
Frm 00075
Fmt 4703
Sfmt 4703
26393
For the U.S. Nuclear Regulatory
Commission.
Brian W. Sheron,
Director, Office of Nuclear Regulatory
Research.
[FR Doc. E6–6747 Filed 5–3–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Report to Congress on Abnormal
Occurrences; Fiscal Year 2005;
Dissemination Of Information
Section 208 of the Energy
Reorganization Act of 1974 (Pub. L. 93–
438) defines an abnormal occurrence
(AO) as an unscheduled incident or
event which the U.S. Nuclear
Regulatory Commission (NRC)
determines to be significant from the
standpoint of public health or safety.
The Federal Reports Elimination and
Sunset Act of 1995 (Pub. L. 104–66)
requires that AOs be reported to
Congress annually. During fiscal year
2005, 9 events that occurred at facilities
licensed or otherwise regulated by the
NRC and/or Agreements States were
determined to be AOs. The report
describes three events at facilities
licensed by the NRC. All three events
occurred at medical institutions. The
first event involved a patient who
received the incorrect dose distribution
while undergoing therapeutic
brachytherapy 1 treatment. The second
event involved an infant who was
administered the incorrect diagnostic
dosage of technetium-99m. The third
event involved three patients who
received unintended radiation doses to
the skin of their thighs while
undergoing therapeutic treatment. The
report also addresses 6 AOs at facilities
licensed by Agreement States.
[Agreement States are those States that
have entered into formal agreements
with the NRC pursuant to section 274 of
the Atomic Energy Act (AEA) to regulate
certain quantities of AEA licensed
material at facilities located within their
borders.] Currently, there are 34
Agreement States. During Fiscal Year
2005, Agreement States reported six
events that occurred at Agreement Statelicensed facilities, including five
therapeutic medical events and one
diagnostic medical event. All six events
met the criteria for AO categorization.
As required by section 208, the
1 Brachytherapy means a method of radiation
therapy in which sources are used to deliver a
radiation dose at a distance of up to a few
centimeters by placement of sources on the body
surface, in natural body cavities, or by placement
directly in tissues.
E:\FR\FM\04MYN1.SGM
04MYN1
Agencies
[Federal Register Volume 71, Number 86 (Thursday, May 4, 2006)]
[Notices]
[Pages 26392-26393]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-6747]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Regulatory Guide: Issuance, Availability
The U.S. Nuclear Regulatory Commission (NRC) has issued a revision
to an existing 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 NRCs 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.
Revision 1 of 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,
describes a method that the NRC staff considers acceptable for use in
complying with the Commission's requirements in Title 10, section
50.69, of the Code of Federal Regulations (Sec. 50.69), with respect
to the categorization of structures, systems, and components (SSCs)
that are considered in risk-informing special treatment requirements.
This categorization method uses the process that the Nuclear Energy
Institute (NEI) described in Revision 0 of its guidance document NEI
00-04, ``10 CFR 50.69 SSC Categorization Guideline,'' dated July
2005.\1\ Specifically, this process determines the safety significance
of SSCs and categorizes them into one of four risk-informed safety
class (RISC) categories.
---------------------------------------------------------------------------
\1\ NEI 00-04, ``10 CFR 50.69 SSC Categorization Guideline,'' is
available through the NRC's Agencywide Documents Access and
Management System (ADAMS), https://www.nrc.gov/reading-rm/adams/web-
based.html, under Accession ML052910035.
---------------------------------------------------------------------------
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 SSCs perform their design-basis
functions. Under this framework, licensees using a risk-informed
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.\2\ In that Commission paper, the NRC staff recommended
developing risk-informed approaches to the application of special
treatment requirements to reduce
[[Page 26393]]
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.
---------------------------------------------------------------------------
\2\ 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/.
---------------------------------------------------------------------------
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 Sec. 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).
The NRC issued a draft of this guide, Draft Regulatory Guide DG-
1121, for public review and comment as part of the Sec. 50.69
rulemaking package in May 2003. The staff subsequently received and
addressed public comments in developing the previous revision of this
guide, which the agency published in January 2006, and has since
incorporated additional stakeholder comments in preparing the current
revision. However, since this is a new regulatory approach to
categorizing SSCs, and to ensure that the final guidance adequately
addresses lessons learned from the initial applications, the NRC
decided to issue this guide for trial use. Therefore, this trial
regulatory guide does not establish any final staff positions for
purposes of the Backfit Rule, 10 CFR 50.109, and may continue to be
revised in response to experience with its use. As such, any changes to
this trial guide prior to staff adoption in final form will not be
considered to be backfits as defined in 10 CFR 50.109(a)(1). This will
ensure that the final regulatory guide adequately addresses lessons
learned from regulatory review of pilot and follow-on applications, and
that the guidance is sufficient to enhance regulatory stability in the
review, approval, and implementation of probabilistic risk assessments
(PRAs) and their results in the risk-informed categorization process
required by Sec. 50.69.
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 Revision 1 of Regulatory
Guide 1.201 may be directed to Donald G. Harrison at (301) 415-3587 or
via e-mail to DGH@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 Revision 1 of
Regulatory Guide 1.201 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 ML061090627.
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 e-
mail 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.
Authority: 5 U.S.C. 552(a).
Dated at Rockville, Maryland, this 1st day of May, 2006.
For the U.S. Nuclear Regulatory Commission.
Brian W. Sheron,
Director, Office of Nuclear Regulatory Research.
[FR Doc. E6-6747 Filed 5-3-06; 8:45 am]
BILLING CODE 7590-01-P