Final Regulatory Guide; Issuance, Availability, 39373-39374 [E6-10908]

Download as PDF sroberts on PROD1PC70 with NOTICES Federal Register / Vol. 71, No. 133 / Wednesday, July 12, 2006 / Notices with the changes in ER Revision 6, i.e., the new cooling system for Unit 3 and the increase in the maximum power level described in the PPE. The evaluation in the SDEIS addresses the wet and dry cooling system for Unit 3 and modifies the analysis of impacts related to the power level increase for both Units 3 and 4. There is no change to the cooling system for Unit 4. These revised evaluations will be incorporated into the final EIS. The final EIS will also set forth the public comments on the analysis presented in this SDEIS received within the comment period described below, together with comments concerning the draft EIS received within the draft EIS comment period, and the staff’s responses to comments. The staff will address comments on portions of the DEIS not affected by the changes in Revisions 6 and 7 of the application in the FEIS only to the extent such comments were received during the comment period on the DEIS or there is otherwise time for the staff to address them. The purpose of this notice is to inform the public that the SDEIS is available for public inspection and comment. The DSEIS is available in the NRC Public Document Room (PDR) located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, 20852, or from the Publicly Available Records (PARS) component of NRC’s Agencywide Documents Access and Management System (ADAMS Accession No. ML061800217), and will also be placed directly on the NRC Web site at https://www.nrc.gov. ADAMS is accessible from the NRC Web site at https://www.nrc.gov/reading-rm/ adams.html (the Public Electronic Reading Room). Persons who do not have access to ADAMS, or who encounter problems in accessing the documents located in ADAMS, should contact the PDR reference staff at 1– 800–397–4209, 301–415–4737, or by email to pdr@nrc.gov. In addition, the Louisa County Library, located at 881 Davis Highway, Mineral, Virginia, has agreed to make the DSEIS available for public inspection. The NRC staff will hold a public meeting to present an overview of the SDEIS and to accept public comments on the DSEIS. The public meeting will be held in the Forum at the Louisa County Middle School, 1009 Davis Highway, Mineral, Virginia on Tuesday, August 15, 2006. The meeting will convene at 7:00 p.m. and will continue until 10:00 p.m., as necessary. The meeting will be transcribed and will include: (1) A presentation of the contents of the SDEIS, and (2) the opportunity for interested government VerDate Aug<31>2005 18:23 Jul 11, 2006 Jkt 208001 agencies, organizations, and individuals to provide comments on the draft report. Additionally, the NRC staff will host informal discussions 1 hour before the start of the meeting at the Louisa County Middle School. No formal comments on the SDEIS will be accepted during the informal discussions. To be considered, comments must be provided either at the transcribed public meeting or in writing. Persons may register to attend or present oral comments at the meeting by contacting Mr. Jack Cushing, by telephone at 1–800–368–5642, extension 1424, or by Internet to the NRC at North_Anna_comments@nrc.gov no later than August 10, 2006. Members of the public may also register to speak at the meeting within 15 minutes of the start of the meeting. Individual oral comments may be limited by the time available, depending on the number of persons who register. Members of the public who have not registered may also have an opportunity to speak, if time permits. Mr. Cushing must be contacted no later than August 7, 2006, if special equipment or accommodations are needed to attend or present information at the public meeting, so that the NRC staff can determine whether the request can be accommodated. Any interested party may submit comments on this report for consideration by the NRC staff. Comments may be accompanied by additional relevant information or supporting data. This draft report is being issued by the NRC for a 45-day comment period. The comment period begins on the date that the U.S. Environmental Protection Agency publishes a Notice of Filing in the Federal Register which is expected to be July 14, 2006; such Notices are published every Friday. The Notice will identify the comment period end date. Members of the public may send written comments on the SDEIS for the North Anna ESP to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, Mailstop T–6D59, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, and should cite the publication date and page number of this Federal Register Notice. Comments may also be delivered to Room T–6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. during Federal workdays. Electronic comments may be sent by the Internet to the NRC at North_Anna_comments@nrc.gov. To assist the NRC staff in identifying and considering issue and concerns, comments on the supplement to the PO 00000 Frm 00094 Fmt 4703 Sfmt 4703 39373 draft EIS should be as specific as possible. It is also helpful if comments refer to specific pages or chapters of the draft supplement. Comments will be available electronically and accessible through the NRC’s PERR link at https:// www.nrc.gov/reading-rm/adams.html. For Further Information Contact: For further information regarding the environmental impact statement, contact Mr. Jack Cushing, Senior Environmental Project Manager, at telephone number 301–415–1424, or by mail at U.S. Nuclear Regulatory Commission, ATTN: Jack Cushing, Mail Stop 0–11F1, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. Dated at Rockville, Maryland, this 6th day of July 2006. For the Nuclear Regulatory Commission. David B. Matthews, Director, Division of New Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E6–10909 Filed 7–11–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Final 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 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. Revision 4 of Regulatory Guide 1.97, entitled ‘‘Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,’’ describes a method that the NRC staff considers acceptable for use in complying with the agency’s regulations with respect to satisfying criteria for accident monitoring instrumentation in nuclear power plants. Specifically, the method described in this regulatory guide relates to General Design Criteria 13, 19, and 64, as set forth in Appendix A to Title 10, Part 50, of the Code of Federal Regulations (10 CFR part 50), ‘‘Domestic Licensing of Production and Utilization Facilities.’’ In addition, Subsection (2)(xix) of 10 CFR 50.34(f), ‘‘Additional TMI-Related Requirements,’’ requires operating reactor licensees to provide adequate instrumentation for use in E:\FR\FM\12JYN1.SGM 12JYN1 39374 Federal Register / Vol. 71, No. 133 / Wednesday, July 12, 2006 / Notices sroberts on PROD1PC70 with NOTICES monitoring plant conditions following an accident that includes core damage. This revision of Regulatory Guide 1.97 represents an ongoing evolution in the nuclear industry’s thinking and approaches with regard to accident monitoring systems for nuclear power plants. Specifically, this revision endorses (with certain clarifying regulatory positions specified in Section C of the revised guide) the ‘‘Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations,’’ which the Institute of Electrical and Electronics Engineers (IEEE) promulgated as IEEE Std. 497–2002. This revised regulatory guide is intended for licensees of new nuclear power plants.1 Previous revisions of this regulatory guide remain in effect for licensees of current operating reactors,1 who are unaffected by this proposed revision. (See regulatory position #1 in Section C of the revised guide for information regarding the applicability of IEEE Std. 497–2002 for current operating reactors.) The NRC previously solicited public comment on this revised guide by publishing a Federal Register notice (70 FR 49953) concerning Draft Regulatory Guide DG–1128 on August 25, 2005. Following the closure of the public comment period on October 14, 2005, the staff considered all stakeholder comments in the course of preparing Revision 4 of Regulatory Guide 1.97. The staff’s responses to all comments received are available in the NRC’s Agencywide Documents Access and Management System (ADAMS) at https://www.nrc.gov/reading-rm/ adams.html, under Accession #ML061580516. 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 1 The terms ‘‘new nuclear power plant’’ and ‘‘new plant’’ refer to any nuclear power plant for which the licensee obtained an operating license after the NRC issued Revision 4 of Regulatory Guide 1.97. The terms ‘‘current operating reactor’’ and ‘‘current plant’’ refer to any nuclear power plant for which the licensee obtained an operating license before the NRC issued Revision 4 of Regulatory Guide 1.97. VerDate Aug<31>2005 18:23 Jul 11, 2006 Jkt 208001 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 4 of Regulatory Guide 1.97 may be directed to Barry S. Marcus at (301) 415–2823 or BSM@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 4 of Regulatory Guide 1.97 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 #ML061580448. 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. (5 U.S.C. 552(a)) Dated at Rockville, Maryland, this 19th day of June, 2006. For the U.S. Nuclear Regulatory Commission. Brian W. Sheron, Director, Office of Nuclear Regulatory Research. [FR Doc. E6–10908 Filed 7–11–06; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00095 Fmt 4703 Sfmt 4703 SECURITIES AND EXCHANGE COMMISSION [Release No. 34–54104; File No. SR–Amex– 2006–47] Self-Regulatory Organizations; American Stock Exchange LLC; Notice of Filing of Proposed Rule Change and Amendment No. 2 Thereto Relating to the Member Firm Guarantee for FLEX Equity Options July 5, 2006. Pursuant to section 19(b)(1) of the Securities Exchange Act of 1934 (‘‘Act’’),1 and Rule 19b–4 thereunder,2 notice is hereby given that on May 12, 2006, the American Stock Exchange LLC (‘‘Amex’’ or ‘‘Exchange’’) filed with the Securities and Exchange Commission (‘‘Commission’’) the proposed rule change as described in Items I, II, and III below, which Items have been prepared by the Amex. The Amex filed Amendment No. 1 to the proposed rule change on June 5, 2006 and subsequently withdrew Amendment No. 1. The Amex filed Amendment No. 2 to the proposed rule change on June 12, 2006.3 The Commission is publishing this notice to solicit comments on the proposed rule change, as amended, from interested persons. I. Self-Regulatory Organization’s Statement of the Terms of Substance of the Proposed Rule Change The Exchange proposes to amend Amex Rule 904G(e)(iii) to change the current member firm guarantee for FLEX equity options to 40%. The text of the proposed rule change is available on the Amex’s Web site (https:// www.amex.com), at the Amex’s Office of the Secretary, and at the Commission’s Public Reference Room. II. Self-Regulatory Organization’s Statement of the Purpose of, and Statutory Basis for, the Proposed Rule Change In its filing with the Commission, the Amex included statements concerning the purpose of and basis for the proposed rule change and discussed any comments it received on the proposed rule change. The text of these statements may be examined at the places specified in Item IV below. The Amex has prepared summaries, set forth in Sections A, B, and C below, of the most significant aspects of such statements.4 1 15 U.S.C. 78s(b)(1). CFR 240.19b–4. 3 In Amendment No. 2, the Amex made technical corrections to the rule text of the proposed rule change. 4 Pursuant to discussions with Amex staff, the Commission made clarifying changes to the purpose 2 17 E:\FR\FM\12JYN1.SGM 12JYN1

Agencies

[Federal Register Volume 71, Number 133 (Wednesday, July 12, 2006)]
[Notices]
[Pages 39373-39374]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-10908]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION


Final 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 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.
    Revision 4 of Regulatory Guide 1.97, entitled ``Criteria for 
Accident Monitoring Instrumentation for Nuclear Power Plants,'' 
describes a method that the NRC staff considers acceptable for use in 
complying with the agency's regulations with respect to satisfying 
criteria for accident monitoring instrumentation in nuclear power 
plants. Specifically, the method described in this regulatory guide 
relates to General Design Criteria 13, 19, and 64, as set forth in 
Appendix A to Title 10, Part 50, of the Code of Federal Regulations (10 
CFR part 50), ``Domestic Licensing of Production and Utilization 
Facilities.'' In addition, Subsection (2)(xix) of 10 CFR 50.34(f), 
``Additional TMI-Related Requirements,'' requires operating reactor 
licensees to provide adequate instrumentation for use in

[[Page 39374]]

monitoring plant conditions following an accident that includes core 
damage.
    This revision of Regulatory Guide 1.97 represents an ongoing 
evolution in the nuclear industry's thinking and approaches with regard 
to accident monitoring systems for nuclear power plants. Specifically, 
this revision endorses (with certain clarifying regulatory positions 
specified in Section C of the revised guide) the ``Criteria for 
Accident Monitoring Instrumentation for Nuclear Power Generating 
Stations,'' which the Institute of Electrical and Electronics Engineers 
(IEEE) promulgated as IEEE Std. 497-2002.
    This revised regulatory guide is intended for licensees of new 
nuclear power plants.\1\ Previous revisions of this regulatory guide 
remain in effect for licensees of current operating reactors,\1\ who 
are unaffected by this proposed revision. (See regulatory position 
1 in Section C of the revised guide for information regarding 
the applicability of IEEE Std. 497-2002 for current operating 
reactors.)
---------------------------------------------------------------------------

    \1\ The terms ``new nuclear power plant'' and ``new plant'' 
refer to any nuclear power plant for which the licensee obtained an 
operating license after the NRC issued Revision 4 of Regulatory 
Guide 1.97. The terms ``current operating reactor'' and ``current 
plant'' refer to any nuclear power plant for which the licensee 
obtained an operating license before the NRC issued Revision 4 of 
Regulatory Guide 1.97.
---------------------------------------------------------------------------

    The NRC previously solicited public comment on this revised guide 
by publishing a Federal Register notice (70 FR 49953) concerning Draft 
Regulatory Guide DG-1128 on August 25, 2005. Following the closure of 
the public comment period on October 14, 2005, the staff considered all 
stakeholder comments in the course of preparing Revision 4 of 
Regulatory Guide 1.97. The staff's responses to all comments received 
are available in the NRC's Agencywide Documents Access and Management 
System (ADAMS) at https://www.nrc.gov/reading-rm/adams.html, under 
Accession ML061580516.
    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 4 of Regulatory 
Guide 1.97 may be directed to Barry S. Marcus at (301) 415-2823 or 
BSM@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 4 of 
Regulatory Guide 1.97 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 ML061580448.
    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.

(5 U.S.C. 552(a))

    Dated at Rockville, Maryland, this 19th day of June, 2006.

    For the U.S. Nuclear Regulatory Commission.
Brian W. Sheron,
Director, Office of Nuclear Regulatory Research.
 [FR Doc. E6-10908 Filed 7-11-06; 8:45 am]
BILLING CODE 7590-01-P
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