Final Regulatory Guides: Impending Issuance, Availability, and Applicability to New Reactor Licensing, 6620-6622 [E7-2372]

Download as PDF 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, http://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 http://www.nrc.gov/ reading-rm/doc-collections/reg-guides/. • The NRC’s Agencywide Document Access and Management System (ADAMS), at http://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 http://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 http://
www.nrc.gov/reading-rm/doc-collections/reg-guides/.
     The NRC's Agencywide Document Access and Management System 
(ADAMS), at http://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 http://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