Final Regulatory Guides: Impending Issuance, Availability, and Applicability to New Reactor Licensing, 6620-6622 [E7-2372]
Download as PDF
<![CDATA[
6620
Federal Register / Vol. 72, No. 28 / Monday, February 12, 2007 / Notices
Alternatives to Proposed Action
As an alternative to the proposed
action, the NRC staff considered denial
of the proposed EPU (i.e., the ‘‘noaction’’ alternative). Denial of the
application would result in no change
in the current environmental impacts.
However, if the EPU were not approved,
other agencies and electric power
organizations may be required to pursue
other means of providing electric
generation capacity to offset future
demand. Fossil fuel plants routinely
emit atmospheric pollutants, causing
impacts in air quality that are larger
than if BFN were to provide the same
amount of electric generation.
Construction and operation of a fossil
fuel plant also create impacts in land
use and waste management. Other
alternatives, such as purchased
electrical power, wind power, and
hydropower, were considered during
the NRC’s review for the BFN license
renewal. The proposed EPU, like license
renewal, would incur fewer
environmental costs than the
alternatives considered. While the EPU
would produce additional spent fuel,
the additional amount of spent fuel
would be stored in a new dry cask
storage facility, which would be
constructed even if the EPU were not
approved. Therefore, the proposed EPU
would not have significant
environmental impacts.
Alternative Use of Resources
This action does not involve the use
of any resources not previously
considered in the SEIS.
sroberts on PROD1PC70 with NOTICES
Agencies and Persons Consulted
In accordance with its stated policy,
on August 7, 2006, the NRC staff
consulted with the Alabama State
official, Mr. Kirk Whatley, of the Office
of Radiation Control, regarding the
environmental impacts of the proposed
action. The State official had no
comments.
Finding of No Significant Impact
On the basis of the EA, the
Commission concludes that the
proposed action would not have a
significant effect on the quality of the
human environment. Accordingly, the
Commission has determined not to
prepare an Environmental Impact
Statement for the proposed action.
For further details with respect to the
proposed action, see the licensee’s
applications dated June 25 and June 28,
2004, as supplemented by letters dated
August 23, 2004, February 23, April 25,
June 6, and December 19, 2005,
February 1 and 28, March 7, 9, 23, and
31, April 13, May 5 and 11, June 12, 15,
VerDate Aug<31>2005
19:52 Feb 09, 2007
Jkt 211001
23 and 27, July 21, 26, and 31, August
4, 16, 18, and 31, September 1, 15, and
22, and October 3, 5, and 13, 2006.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, 11555 Rockville Pike
(first floor), Rockville, Maryland.
Publicly available records will be
accessible electronically from the
Agencywide Documents Access and
Management System (ADAMS) Public
Electronic Reading Room on the NRC
Web site, https://www.nrc.gov/readingrm/adams.html. Persons who do not
have access to ADAMS or who
encounter problems in accessing the
documents located in ADAMS should
contact the NRC PDR Reference staff at
1–800–397–4209, or 301–415–4737, or
send an e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 6th day
of February 2007.
For the Nuclear Regulatory Commission.
Timothy J. McGinty,
Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E7–2342 Filed 2–9–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Final Regulatory Guides: Impending
Issuance, Availability, and Applicability
to New Reactor Licensing
U.S. Nuclear Regulatory
Commission.
ACTION: Issuance, Availability, and
Applicability of Final Regulatory Guides
for New Reactor Licensing.
AGENCY:
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is currently
reviewing and revising numerous guides
in the agency’s Regulatory Guide (RG)
Series. This series has been developed
to describe, and make available to the
public, 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.
Availability And Dates
The NRC will make each new or
revised RG publicly available through
the following electronic distribution
channels:
• The NRC’s Electronic Reading
Room on the agency’s public Web site,
in the Regulatory Guides document
PO 00000
Frm 00104
Fmt 4703
Sfmt 4703
collection, at https://www.nrc.gov/
reading-rm/doc-collections/reg-guides/.
• The NRC’s Agencywide Document
Access and Management System
(ADAMS), at https://www.nrc.gov/
reading-rm/adams.html (using the
ADAMS accession number specified in
the footer on the first page of each
regulatory guide).
Please note that the NRC does not
intend to distribute printed copies of
these revised RGs unless specifically
requested on an individual basis with
adequate justification. Requests for
single copies 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. In addition,
the NRC does not intend to issue
separate notices of issuance and
availability. Consequently, interested
parties should regularly peruse the
previously specified electronic
distribution channels to identify newly
revised RGs.
RGs are not copyrighted, and
Commission approval is not required to
reproduce them. Copies of each RG and
other related publicly available
documents, including public comments
received, can be viewed electronically
on computers in the NRC’s Public
Document Room (PDR), which is
located at One White Flint North, 11555
Rockville Pike, Rockville, Maryland,
Room O–1 F21, and is open to the
public on Federal workdays from 7:45
a.m. until 4:15 p.m. The PDR
reproduction contractor will make
copies of documents for a fee. Selected
documents, including public comments
on the DGs, can also be viewed and
downloaded electronically via ADAMS
at https://www.nrc.gov/NRC/reading-rm/
adams.html. If you do not have access
to ADAMS or if you encounter problems
in accessing the documents stored in
ADAMS, contact the PDR Reference
Staff at (800) 397–4209 or (301) 415–
4737, or by e-mail to PDR@nrc.gov.
SUPPLEMENTARY INFORMATION: The
revised versions of the RGs will not be
used as a backfit to any previously
issued staff position for existing nuclear
power reactors. The purpose of the
ongoing revision of the NRC’s RGs is to
ensure that prospective applicants have
complete, accurate, and current
guidance for use in preparing early site
permit (ESP), design certification (DC),
and combined license (COL)
applications for proposed new reactors.
In particular, the NRC staff ensures that
the agency’s regulatory guidance is
E:\FR\FM\12FEN1.SGM
12FEN1
Federal Register / Vol. 72, No. 28 / Monday, February 12, 2007 / Notices
consistent with the rulemaking,
‘‘Licenses, Certifications, and Approvals
for Nuclear Power Plants’’ (Title 10, Part
52, of the Code of Federal Regulations
(10 CFR part 52)). The proposed rule
was published in the Federal Register
on March 13, 2006 (71 FR 12781).
Over the past several months, the
NRC has issued drafts of the revised RGs
for a 45-day public comment period.
The NRC staff is currently addressing
the stakeholder comments received on
these RGs.
Discussion
The NRC regulates the siting,
construction, and operation of
commercially owned nuclear power
facilities in the United States through a
combination of regulatory requirements,
licensing, and oversight (including
inspection). These activities enable the
agency to fulfill its mission to license
and regulate the Nation’s civilian use of
byproduct, source, and special nuclear
materials to ensure adequate protection
of public health and safety, promote the
common defense and security, and
protect the environment.
In late 2000, the NRC became aware
that some electric companies were
exploring the option of building new
nuclear power plants in the United
States. As a result, in February 2001, the
Commission issued a staff requirements
memorandum (SRM COMJSM–00–0003)
directing the staff to (1) assess its
technical, licensing, and inspection
capabilities, as well as its readiness to
review new license applications and
inspect new nuclear power plants; (2)
examine the regulatory infrastructure for
10 CFR Parts 50 and 52, as well as other
applicable regulations; and (3) identify
any enhancements needed to ensure
that the agency is prepared to review
ESP, DC, and COL applications for new
nuclear power plants.
In response to the Commission’s SRM,
the staff issued SECY–01–0188, ‘‘Future
Licensing and Inspection Readiness
Assessment’’ (FLIRA), in October 2001.
In addition, although the FLIRA stated
that the staff considers the agency’s
current regulatory infrastructure
adequate to support new reactor
licensing, the staff has undertaken major
infrastructure changes to make new
licensing reviews more effective and
efficient, and to reduce unnecessary
regulatory burden on future applicants.
6621
The staff’s ongoing review and revision
of the NRC’s RGs is one significant
aspect of these infrastructure changes.
Through the years, the NRC has
established 10 broad divisions of RGs, of
which the following are the subject of
the staff’s particular efforts to support
new reactor licensing.
• Division 1, Power Reactors
• Division 4, Environmental and
Siting
• Division 8, Occupational Health
Of these Divisions, the NRC identified
a select group of RGs that required
revision and are currently being
updated to (1) ensure consistency with
the rulemaking to update 10 CFR Part
52; (2) ensure coherence with NUREG–
0800, ‘‘Standard Review Plan for the
Review of Safety Analysis Reports for
Nuclear Power Plants’’ (SRP), which is
also undergoing staff review and
revision; and (3) provide prospective
applicants with complete, accurate, and
current guidance for use in preparing
ESP, DC, and COL applications for
proposed new reactors. Following is a
list of RGs along with the Draft Guide
(DG) numbers used during the public
comment period.
RG
DG title
1.7 DG–1117 .........................................
1.9 DG–1172 .........................................
1.13 DG–1162 .......................................
1.20 DG–1163 .......................................
Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident.
Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants.
Spent Fuel Storage Facility Design Basis.
Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial
Startup Testing.
Meteorological Monitoring Programs for Nuclear Power Plants.
Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing
Components of Nuclear Power Plants.
Seismic Design Classification.
Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of
Water-Cooled Nuclear Power Plants.
Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components.
Damping Values for Seismic Design of Nuclear Power Plants.
Initial Test Programs for Water-Cooled Nuclear Power Plants.
Welder Qualification for Areas of Limited Accessibility.
Design Basis Tornado and Tornado Missiles for Nuclear Power Plants.
Combining Modal Responses and Spatial Components in Seismic Response Analysis.
Availability of Electric Power Sources.
Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants.
Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-WaterCooled Power Reactors.
Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports.
Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants.
Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power
Plants.
Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports.
Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete
Containments.
Fire Protection for Nuclear Power Plants.
Control Room Habitability at Light-Water Nuclear Power Reactors.
An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for
Risk-Informed Activities.
Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants.
Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)—Effluent Streams and the Environment.
DG–1164 .......................................
DG–1152 .......................................
1.29
1.37
DG–1156 .......................................
DG–1165 .......................................
1.57
DG–1158 .......................................
1.61
1.68
1.71
1.76
1.92
1.93
1.97
1.112
DG–1157 .......................................
DG–1166 .......................................
DG–1167 .......................................
DG–1143 .......................................
DG–1127 .......................................
DG–1153 .......................................
DG–1128 .......................................
DG–1160 .....................................
1.124
1.128
1.129
DG–1168 .....................................
DG–1154 .....................................
DG–1155 .....................................
1.130
1.136
sroberts on PROD1PC70 with NOTICES
1.23
1.26
DG–1169 .....................................
DG–1159 .....................................
1.189
1.196
1.200
DG–1170 .....................................
DG–1171 .....................................
DG–1161 .....................................
1.205 DG–1139 .....................................
4.15 DG–4010 .......................................
VerDate Aug<31>2005
19:52 Feb 09, 2007
Jkt 211001
PO 00000
Frm 00105
Fmt 4703
Sfmt 4703
E:\FR\FM\12FEN1.SGM
12FEN1
6622
Federal Register / Vol. 72, No. 28 / Monday, February 12, 2007 / Notices
RG
DG title
The staff is also currently developing the following new RGs to provide prospective applicants with complete, accurate, and current guidance
for use in preparing ESP, DC, and COL applications for proposed new reactors:
1.206
1.207
DG–1145 .....................................
DG–1144 .....................................
1.208
1.209
DG–1146 .....................................
DG–1142 .....................................
Combined License Applications for Nuclear Power Plants (LWR Edition).
Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components
Due to the Effects of the Light Reactor Water Environment for New Reactors.
A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion.
Guidelines for Environmental Qualification of Safety Related Computer-Based Instrumentation and
Control Systems in Nuclear Power Plants.
Dated at Rockville, Maryland, this 2nd day
of February, 2007.
For the U.S. Nuclear Regulatory
Commission,
Farouk Eltawila,
Director, Division of Risk Assessment and
Special Projects, Office of Nuclear Regulatory
Research.
[FR Doc. E7–2372 Filed 2–9–07; 8:45 am]
Comment Procedures
sroberts on PROD1PC70 with NOTICES
The NRC finalized and published
Revision 2 of RG 1.92 (July 2006),
Revision 4 of RG 1.97 (July 2006),
Revision 1 to RG 1.196 and Revision 1
of RG 1.200 (January 2007), and RG
1.205 (June 2006). The NRC plans to
issue the remaining revised RGs as they
are finalized between February and
March of 2007. The staff has determined
that the RGs listed previously may be
uniformly applied (consistent with the
staff guidance provided in the SRP) to
the ESP, DC, and COL applications
submitted for proposed new reactors.
Andean Trade Preference Act (ATPA),
as Amended: Request for Public
Comments Regarding Beneficiary
Countries
The NRC staff encourages and
welcomes comments and suggestions in
connection with improvements to
published RGs, as well as items for
inclusion in RGs that are currently being
developed. You may submit comments
by any of the following methods:
• Mail comments to Rulemaking,
Directives, and Editing Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001 (MS T–6 D59).
• Hand-deliver comments to
Rulemaking, Directives, and Editing
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 Rulemaking,
Directives and Editing Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, at (301) 415–5144.
• E-mail comments to
NRCREP@nrc.gov.
Contact Information: Contact
information for use in obtaining printed
or electronic copies of the revised RGs
is provided in the section on
Availability And Dates. Contact
information for use in submitting
comments is provided in the section on
Comment Procedures. Comments or
questions about the NRC’s revision of
RGs to support new reactor licensing
should be addressed to Jimi T. Yerokun
at (301) 415–0585 or by e-mail to
JTY@nrc.gov.
(5 U.S.C. 552(a))
VerDate Aug<31>2005
19:52 Feb 09, 2007
Jkt 211001
BILLING CODE 7590–01–P
OFFICE OF THE UNITED STATES
TRADE REPRESENTATIVE
Office of the United States
Trade Representatives
ACTION: Notice; request for comments.
AGENCY:
SUMMARY: In compliance with section
203(f) of the ATPA, as amended, 19
U.S.C. 3202(f)(2), the Office of the
United States Trade Representative
(USTR) is requesting the views of
interested parties on whether the
designated beneficiary countries are
meeting the eligibility criteria under the
ATPA., (See 19 U.S.C. 3203(b)(6)(B).)
This information will be used in the
preparation of a report to the Congress
on the operation of the program.
DATES: Public comments are due at
USTR no later than 5 p.m., March 5,
2007.
ADDRESSES: Submit comments by
electronic mail (e-mail) to:
FR0518@USTR.EOP.GOV. For
assistance or if unable to submit
comments by e-mail, fax your comments
to Gloria Blue, Executive Secretary,
Trade Policy Staff Committee, at (202)
395–6143.
FOR FURTHER INFORMATION CONTACT:
Michelle Carrillo, Office of the
Americas, Office of the United States
Trade Representative, 600 17th Street,
NW., Room 523, Washington, DC 20508.
The telephone number is (202) 395–
9479.
SUPPLEMENTARY INFORMATION: The
ATPA, as amended by the Andean
PO 00000
Frm 00106
Fmt 4703
Sfmt 4703
Trade Promotion and Drug Eradication
Act of 2002 (ATPDEA) in the Trade Act
of 2002, 19 U.S.C. 3201 et seq., provides
trade benefits for eligible Andean
countries. In Proclamation 7616 of
October 31, 2002, the President
designated Bolivia, Colombia, Ecuador,
and Peru as ATPDEA beneficiary
countries. Section 203(f) of the ATPA
(19 U.S.C. 3202(f)) requires the USTR,
not later than April 30, 2007, to submit
to Congress a report on the operation of
the ATPA. Before submitting such
report, USTR is required to request
comments on whether beneficiary
countries are meeting the criteria set
forth in 19 U.S.C. 3203(b)(6)(B) (which
incorporates by reference the criteria set
forth in sections 3202(c) and (d)). USTR
refers interested parties to the Federal
Register notice published on August 15,
2002 (67 FR 53379)), for a full list of the
eligibility criteria.
Required for Submissions. In order to
facilitate prompt processing of
submissions, USTR strongly urges and
prefers electronic (e-mail) submissions
in response to this notice. In the event
that an e-mail submission is impossible,
submissions should be made by
facsimile.
Persons making submissions by email should use the following subject
line: ‘‘ATPA Beneficiary Countries.’’
Documents should be submitted as
either WordPerfect, MSWord, Adobe
PDF, or text (.TXT) files. Spreadsheets
submitted as supporting documentation
are acceptable as Quattro Pro or Excel.
If any document submitted
electronically contains business
confidential information, the file name
of the business confidential version
should begin with the characters ‘‘BC-’’,
and the file name of the public version
should begin with the characters ‘‘P-’’.
The ‘‘P-’’ or ‘‘BC-’’ should be followed
by the name of the submitter. Persons
who make submissions by e-mail should
not provide separate cover letters;
information that might appear in a cover
letter should be included in the
submission itself. To the extent
possible, any attachments to the
submission should be included in the
E:\FR\FM\12FEN1.SGM
12FEN1
]]>Agencies
[Federal Register Volume 72, Number 28 (Monday, February 12, 2007)]
[Notices]
[Pages 6620-6622]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-2372]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Final Regulatory Guides: Impending Issuance, Availability, and
Applicability to New Reactor Licensing
AGENCY: U.S. Nuclear Regulatory Commission.
ACTION: Issuance, Availability, and Applicability of Final Regulatory
Guides for New Reactor Licensing.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is currently
reviewing and revising numerous guides in the agency's Regulatory Guide
(RG) Series. This series has been developed to describe, and make
available to the public, 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.
Availability And Dates
The NRC will make each new or revised RG publicly available through
the following electronic distribution channels:
The NRC's Electronic Reading Room on the agency's public
Web site, in the Regulatory Guides document collection, at https://
www.nrc.gov/reading-rm/doc-collections/reg-guides/.
The NRC's Agencywide Document Access and Management System
(ADAMS), at https://www.nrc.gov/reading-rm/adams.html (using the ADAMS
accession number specified in the footer on the first page of each
regulatory guide).
Please note that the NRC does not intend to distribute printed
copies of these revised RGs unless specifically requested on an
individual basis with adequate justification. Requests for single
copies 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. In
addition, the NRC does not intend to issue separate notices of issuance
and availability. Consequently, interested parties should regularly
peruse the previously specified electronic distribution channels to
identify newly revised RGs.
RGs are not copyrighted, and Commission approval is not required to
reproduce them. Copies of each RG and other related publicly available
documents, including public comments received, can be viewed
electronically on computers in the NRC's Public Document Room (PDR),
which is located at One White Flint North, 11555 Rockville Pike,
Rockville, Maryland, Room O-1 F21, and is open to the public on Federal
workdays from 7:45 a.m. until 4:15 p.m. The PDR reproduction contractor
will make copies of documents for a fee. Selected documents, including
public comments on the DGs, can also be viewed and downloaded
electronically via ADAMS at https://www.nrc.gov/NRC/reading-rm/
adams.html. If you do not have access to ADAMS or if you encounter
problems in accessing the documents stored in ADAMS, contact the PDR
Reference Staff at (800) 397-4209 or (301) 415-4737, or by e-mail to
PDR@nrc.gov.
SUPPLEMENTARY INFORMATION: The revised versions of the RGs will not be
used as a backfit to any previously issued staff position for existing
nuclear power reactors. The purpose of the ongoing revision of the
NRC's RGs is to ensure that prospective applicants have complete,
accurate, and current guidance for use in preparing early site permit
(ESP), design certification (DC), and combined license (COL)
applications for proposed new reactors. In particular, the NRC staff
ensures that the agency's regulatory guidance is
[[Page 6621]]
consistent with the rulemaking, ``Licenses, Certifications, and
Approvals for Nuclear Power Plants'' (Title 10, Part 52, of the Code of
Federal Regulations (10 CFR part 52)). The proposed rule was published
in the Federal Register on March 13, 2006 (71 FR 12781).
Over the past several months, the NRC has issued drafts of the
revised RGs for a 45-day public comment period. The NRC staff is
currently addressing the stakeholder comments received on these RGs.
Discussion
The NRC regulates the siting, construction, and operation of
commercially owned nuclear power facilities in the United States
through a combination of regulatory requirements, licensing, and
oversight (including inspection). These activities enable the agency to
fulfill its mission to license and regulate the Nation's civilian use
of byproduct, source, and special nuclear materials to ensure adequate
protection of public health and safety, promote the common defense and
security, and protect the environment.
In late 2000, the NRC became aware that some electric companies
were exploring the option of building new nuclear power plants in the
United States. As a result, in February 2001, the Commission issued a
staff requirements memorandum (SRM COMJSM-00-0003) directing the staff
to (1) assess its technical, licensing, and inspection capabilities, as
well as its readiness to review new license applications and inspect
new nuclear power plants; (2) examine the regulatory infrastructure for
10 CFR Parts 50 and 52, as well as other applicable regulations; and
(3) identify any enhancements needed to ensure that the agency is
prepared to review ESP, DC, and COL applications for new nuclear power
plants.
In response to the Commission's SRM, the staff issued SECY-01-0188,
``Future Licensing and Inspection Readiness Assessment'' (FLIRA), in
October 2001. In addition, although the FLIRA stated that the staff
considers the agency's current regulatory infrastructure adequate to
support new reactor licensing, the staff has undertaken major
infrastructure changes to make new licensing reviews more effective and
efficient, and to reduce unnecessary regulatory burden on future
applicants. The staff's ongoing review and revision of the NRC's RGs is
one significant aspect of these infrastructure changes.
Through the years, the NRC has established 10 broad divisions of
RGs, of which the following are the subject of the staff's particular
efforts to support new reactor licensing.
Division 1, Power Reactors
Division 4, Environmental and Siting
Division 8, Occupational Health
Of these Divisions, the NRC identified a select group of RGs that
required revision and are currently being updated to (1) ensure
consistency with the rulemaking to update 10 CFR Part 52; (2) ensure
coherence with NUREG-0800, ``Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear Power Plants'' (SRP), which is also
undergoing staff review and revision; and (3) provide prospective
applicants with complete, accurate, and current guidance for use in
preparing ESP, DC, and COL applications for proposed new reactors.
Following is a list of RGs along with the Draft Guide (DG) numbers used
during the public comment period.
------------------------------------------------------------------------
RG DG title
------------------------------------------------------------------------
1.7 DG-1117.......................... Control of Combustible Gas
Concentrations in Containment
Following a Loss-of-Coolant
Accident.
1.9 DG-1172.......................... Application and Testing of Safety-
Related Diesel Generators in
Nuclear Power Plants.
1.13 DG-1162......................... Spent Fuel Storage Facility
Design Basis.
1.20 DG-1163......................... Comprehensive Vibration
Assessment Program for Reactor
Internals During Preoperational
and Initial Startup Testing.
1.23 DG-1164......................... Meteorological Monitoring
Programs for Nuclear Power
Plants.
1.26 DG-1152......................... Quality Group Classifications and
Standards for Water-, Steam-,
and Radioactive-Waste-Containing
Components of Nuclear Power
Plants.
1.29 DG-1156......................... Seismic Design Classification.
1.37 DG-1165......................... Quality Assurance Requirements
for Cleaning of Fluid Systems
and Associated Components of
Water-Cooled Nuclear Power
Plants.
1.57 DG-1158......................... Design Limits and Loading
Combinations for Metal Primary
Reactor Containment System
Components.
1.61 DG-1157......................... Damping Values for Seismic Design
of Nuclear Power Plants.
1.68 DG-1166......................... Initial Test Programs for Water-
Cooled Nuclear Power Plants.
1.71 DG-1167......................... Welder Qualification for Areas of
Limited Accessibility.
1.76 DG-1143......................... Design Basis Tornado and Tornado
Missiles for Nuclear Power
Plants.
1.92 DG-1127......................... Combining Modal Responses and
Spatial Components in Seismic
Response Analysis.
1.93 DG-1153......................... Availability of Electric Power
Sources.
1.97 DG-1128......................... Criteria for Accident Monitoring
Instrumentation for Nuclear
Power Plants.
1.112 DG-1160........................ Calculation of Releases of
Radioactive Materials in Gaseous
and Liquid Effluents from Light-
Water-Cooled Power Reactors.
1.124 DG-1168........................ Service Limits and Loading
Combinations for Class 1 Linear-
Type Component Supports.
1.128 DG-1154........................ Installation Design and
Installation of Vented Lead-Acid
Storage Batteries for Nuclear
Power Plants.
1.129 DG-1155........................ Maintenance, Testing, and
Replacement of Vented Lead-Acid
Storage Batteries for Nuclear
Power Plants.
1.130 DG-1169........................ Service Limits and Loading
Combinations for Class 1 Plate-
and-Shell-Type Component
Supports.
1.136 DG-1159........................ Design Limits, Loading
Combinations, Materials,
Construction, and Testing of
Concrete Containments.
1.189 DG-1170........................ Fire Protection for Nuclear Power
Plants.
1.196 DG-1171........................ Control Room Habitability at
Light-Water Nuclear Power
Reactors.
1.200 DG-1161........................ An Approach for Determining the
Technical Adequacy of
Probabilistic Risk Assessment
Results for Risk-Informed
Activities.
1.205 DG-1139........................ Risk-Informed, Performance-Based
Fire Protection for Existing
Light-Water Nuclear Power
Plants.
4.15 DG-4010......................... Quality Assurance for
Radiological Monitoring Programs
(Inception through Normal
Operations to License
Termination)--Effluent Streams
and the Environment.
------------------------------------------------------------------------
[[Page 6622]]
The staff is also currently developing the following new RGs to provide
prospective applicants with complete, accurate, and current guidance
for use in preparing ESP, DC, and COL applications for proposed new
reactors:
------------------------------------------------------------------------
1.206 DG-1145........................ Combined License Applications for
Nuclear Power Plants (LWR
Edition).
1.207 DG-1144........................ Guidelines for Evaluating Fatigue
Analyses Incorporating the Life
Reduction of Metal Components
Due to the Effects of the Light
Reactor Water Environment for
New Reactors.
1.208 DG-1146........................ A Performance-Based Approach to
Define the Site-Specific
Earthquake Ground Motion.
1.209 DG-1142........................ Guidelines for Environmental
Qualification of Safety Related
Computer-Based Instrumentation
and Control Systems in Nuclear
Power Plants.
------------------------------------------------------------------------
The NRC finalized and published Revision 2 of RG 1.92 (July 2006),
Revision 4 of RG 1.97 (July 2006), Revision 1 to RG 1.196 and Revision
1 of RG 1.200 (January 2007), and RG 1.205 (June 2006). The NRC plans
to issue the remaining revised RGs as they are finalized between
February and March of 2007. The staff has determined that the RGs
listed previously may be uniformly applied (consistent with the staff
guidance provided in the SRP) to the ESP, DC, and COL applications
submitted for proposed new reactors.
Comment Procedures
The NRC staff encourages and welcomes comments and suggestions in
connection with improvements to published RGs, as well as items for
inclusion in RGs that are currently being developed. You may submit
comments by any of the following methods:
Mail comments to Rulemaking, Directives, and Editing
Branch, Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001 (MS T-6 D59).
Hand-deliver comments to Rulemaking, Directives, and
Editing 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 Rulemaking, Directives and Editing Branch,
Office of Administration, U.S. Nuclear Regulatory Commission, at (301)
415-5144.
E-mail comments to NRCREP@nrc.gov.
Contact Information: Contact information for use in obtaining
printed or electronic copies of the revised RGs is provided in the
section on Availability And Dates. Contact information for use in
submitting comments is provided in the section on Comment Procedures.
Comments or questions about the NRC's revision of RGs to support new
reactor licensing should be addressed to Jimi T. Yerokun at (301) 415-
0585 or by e-mail to JTY@nrc.gov.
(5 U.S.C. 552(a))
Dated at Rockville, Maryland, this 2nd day of February, 2007.
For the U.S. Nuclear Regulatory Commission,
Farouk Eltawila,
Director, Division of Risk Assessment and Special Projects, Office of
Nuclear Regulatory Research.
[FR Doc. E7-2372 Filed 2-9-07; 8:45 am]
BILLING CODE 7590-01-P
