Office of New Reactors; Interim Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment, 13610-13611 [2010-6200]

Download as PDF 13610 Federal Register / Vol. 75, No. 54 / Monday, March 22, 2010 / Notices pwalker on DSK8KYBLC1PROD with NOTICES construction methods regarding the areas in which work is to be performed, the location of existing infrastructure such as buried power lines, and/or unanticipated delays that could significantly impact the project schedules. These site-specific safety and construction methods must be accounted for in the proposed schedule that, in turn, impacts the final compliance date requested. The licensee has provided a coordinated/combined schedule for all three projects at SQN that outlines the sequence in which work must be conducted to ensure effective system connectivity. The required tasks/changes must be completed in sequence at each site to support all program upgrades being performed and to ensure effective connectivity of each project. The upgrades that the licensee identified within their exemption request support their solution for meeting the requirements. The proposed implementation schedule depicts the critical activity milestones of the security system upgrades; is consistent with the licensee’s solution for meeting the requirements; is consistent with the scope of the modifications and the issues and challenges identified; and is consistent with the licensee’s requested compliance date. Notwithstanding the scheduler exemptions for these limited requirements, the licensee will continue to be in compliance with all other applicable physical security requirements as described in 10 CFR 73.55 and reflected in its current NRC approved physical security program. By September 24, 2012, SQN will be in full compliance with all the regulatory requirements of 10 CFR 73.55, as issued on March 27, 2009. 4.0 Conclusion for Part 73 Schedule Exemption Request The staff has reviewed the licensee’s submittals and concludes that the licensee has provided adequate justification for its request for an extension of the compliance date to September 24, 2012, with regard to two specified requirements of 10 CFR 73.55. Accordingly, the Commission has determined that pursuant to 10 CFR 73.5, the exemption from the March 31, 2010, compliance date is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants the requested exemption. The NRC staff has determined that the long-term benefits that will be realized when the security system upgrades are VerDate Nov<24>2008 16:41 Mar 19, 2010 Jkt 220001 complete justify exceeding the full compliance date in the case of this particular licensee. The security measures SQN needs additional time to implement are new requirements imposed by March 27, 2009, amendments to 10 CFR 73.55, and are in addition to those required by the security orders issued in response to the events of September 11, 2001. Therefore, the NRC staff concludes that the licensee’s actions are in the best interest of protecting the public health and safety through the security changes that will result from granting this exemption. As per the licensee’s request and the NRC’s regulatory authority to grant an exemption from the March 31, 2010, implementation deadline for the two items specified in Enclosure 1 of the TVA letter dated November 6, 2009, as supplemented by letter dated January 11, 2010, the licensee is required to be in full compliance by September 24, 2012. In achieving compliance, the licensee is reminded that it is responsible for determining the appropriate licensing mechanism (i.e., 10 CFR 50.54(p) or 10 CFR 50.90) for incorporation of all necessary changes to its security plans. Pursuant to 10 CFR 51.32, ‘‘Finding of no significant impact,’’ the Commission has previously determined that the granting of this exemption will not have a significant effect on the quality of the human environment (75 FR 3762, dated January 22, 2010). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 11th day of March 2010. For The Nuclear Regulatory Commission. Joseph G. Giitter, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–6190 Filed 3–19–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [DC/COL–ISG–020; NRC–2009–0457] Office of New Reactors; Interim Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of availability. SUMMARY: The NRC is issuing its Final Interim Staff Guidance (ISG) DC/COL– PO 00000 Frm 00128 Fmt 4703 Sfmt 4703 ISG–020 titled ‘‘Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment,’’ (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100491233). This ISG supplements the guidance provided to the staff in Section 19.0 of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,’’ issued March 2007 and DC/ COL–ISG–03, ‘‘Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications,’’ dated June 11, 2008 (ADAMS Accession No. ML081430087) concerning the review of probabilistic risk assessment (PRA) information and severe accident assessments submitted to support design certification (DC) and combined license (COL) applications. The NRC staff intends to incorporate DC/COL– ISG–020 into the next revision of SRP Section 19.0 and Regulatory Guide 1.206, ‘‘Combined License Applications for Nuclear Power Plants (LWR Edition),’’ June 2007. Disposition: On October 16, 2009, the NRC staff issued the proposed ISG, DC/ COL–ISG–020 ‘‘Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment,’’ (ADAMS Accession No. ML092650316) to solicit public and industry comment. The NRC staff received comments on the proposed guidance. This final issuance incorporates changes from the majority of the comments. The NRC staff responses to these comments can be found in ADAMS Accession No. ML100491287. ADDRESSES: The NRC maintains ADAMS, which provides text and image files of NRC’s public documents. These documents may be accessed through the NRC’s Public Electronic Reading Room on the Internet at https://www.nrc.gov/ reading-rm/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 Public Document Room reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail at pdr.resource@nrc.gov. FOR FURTHER INFORMATION CONTACT: Dr. Kimberly A. Hawkins, Chief, Structural Engineering Branch 2, Division of Engineering, Office of the New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone at 301–415–0564 or e-mail at Kimberly.Hawkins@nrc.gov. E:\FR\FM\22MRN1.SGM 22MRN1 Federal Register / Vol. 75, No. 54 / Monday, March 22, 2010 / Notices The agency posts its issued staff guidance in the agency external Web page (https:// www.nrc.gov/reading-rm/doccollections/isg/). SUPPLEMENTARY INFORMATION: Dated at Rockville, Maryland, this 15th day of March 2010. For the Nuclear Regulatory Commission. William F. Burton, Chief, Rulemaking and Guidance Development Branch, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2010–6200 Filed 3–19–10; 8:45 am] BILLING CODE 7590–01–P Dated: March 15, 2010. Antonio F. Dias, Chief, Reactor Safety Branch B, Advisory Committee on Reactor Safeguards. NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Planning and Procedures Subcommittee Meeting; Notice of Meeting [FR Doc. 2010–6186 Filed 3–19–10; 8:45 am] BILLING CODE 7590–01–P pwalker on DSK8KYBLC1PROD with NOTICES The ACRS Planning and Procedures Subcommittee will hold a meeting on April 7, 2010, at Room T2–B1, at 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance, with the exception of a portion that may be closed pursuant to 5 U.S.C. 552b(c)(2) and (6) to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of the ACRS, and information the release of which would constitute a clearly unwarranted invasion of personal privacy. The agenda for the subject meeting shall be as follows: Wednesday, April 7, 2010, 12 p.m.–1 p.m. The Subcommittee will discuss proposed ACRS activities and related matters. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Officer (DFO), Mr. Peter Wen, (Telephone: 301–415–2832, E-mail: Peter.Wen@nrc.gov) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 14, 2009, (74 FR 52829– 52830). Detailed meeting agendas and meeting transcripts are available on the NRC VerDate Nov<24>2008 16:41 Mar 19, 2010 Jkt 220001 Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information regarding topics to be discussed, changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained by contacting the DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with the DFO if such rescheduling would result in major inconvenience. NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Reliability and PRA; Notice of Meeting The ACRS Reliability and PRA Subcommittee will hold a meeting on April 7, 2010, at 11545 Rockville Pike, T2–B1, Rockville, Maryland. The entire meeting will be open to public attendance. The proposed agenda for the subject meeting shall be as follows: Wednesday, April 7, 2010, 8:30 a.m.– 3:30 p.m. The Subcommittee will update on staff’s activities to address differences in various human reliability analysis models. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), Peter Wen (Telephone 301–415–2832, E-mail: Peter.Wen@nrc.gov) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty minutes before the meeting. In addition, one electronic copy of each presentation should be e-mailed to the DFO one day before meeting. If an electronic copy cannot be provided within this timeframe, presenters should provide the DFO with a CD containing each PO 00000 Frm 00129 Fmt 4703 Sfmt 4703 13611 presentation at least thirty minutes before the meeting. Electronic recordings will be permitted. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 14, 2009, (74 FR 58268–58269). Detailed meeting agendas and meeting transcripts are available on the NRC Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information regarding topics to be discussed, changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained from the Web site cited above or by contacting the identified DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with these references if such rescheduling would result in major inconvenience. Dated: March 15, 2010. Antonio F. Dias, Chief, Reactor Safety Branch B, Advisory Committee on Reactor Safeguards. [FR Doc. 2010–6203 Filed 3–19–10; 8:45 am] BILLING CODE 7590–01–P POSTAL REGULATORY COMMISSION [Docket No. MC2010–20; Order No. 423] New Postal Product Postal Regulatory Commission. Notice. AGENCY: ACTION: SUMMARY: The Commission is noticing a recently-filed Postal Service request to transfer selected Post Office Box Service locations from the Market Dominant Product List to the Competitive Product List. This notice addresses procedural steps associated with that filing. DATES: Comments are due: March 31, 2010. ADDRESSES: Submit comments electronically via the Commission’s Filing Online system at https:// www.prc.gov. Commenters who cannot submit their views electronically should contact the person identified in the FOR FURTHER INFORMATION CONTACT section by telephone for advice on alternatives to electronic filing. FOR FURTHER INFORMATION CONTACT: Stephen L. Sharfman, General Counsel, 202–789–6820 or stephen.sharfman@prc.gov. SUPPLEMENTARY INFORMATION: E:\FR\FM\22MRN1.SGM 22MRN1

Agencies

[Federal Register Volume 75, Number 54 (Monday, March 22, 2010)]
[Notices]
[Pages 13610-13611]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-6200]


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NUCLEAR REGULATORY COMMISSION

[DC/COL-ISG-020; NRC-2009-0457]


Office of New Reactors; Interim Staff Guidance on Implementation 
of a Seismic Margin Analysis for New Reactors Based on Probabilistic 
Risk Assessment

AGENCY: Nuclear Regulatory Commission (NRC).

ACTION: Notice of availability.

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

SUMMARY: The NRC is issuing its Final Interim Staff Guidance (ISG) DC/
COL-ISG-020 titled ``Implementation of a Seismic Margin Analysis for 
New Reactors Based on Probabilistic Risk Assessment,'' (Agencywide 
Documents Access and Management System (ADAMS) Accession No. 
ML100491233). This ISG supplements the guidance provided to the staff 
in Section 19.0 of NUREG-0800, ``Standard Review Plan for the Review of 
Safety Analysis Reports for Nuclear Power Plants,'' issued March 2007 
and DC/COL-ISG-03, ``Probabilistic Risk Assessment Information to 
Support Design Certification and Combined License Applications,'' dated 
June 11, 2008 (ADAMS Accession No. ML081430087) concerning the review 
of probabilistic risk assessment (PRA) information and severe accident 
assessments submitted to support design certification (DC) and combined 
license (COL) applications. The NRC staff intends to incorporate DC/
COL-ISG-020 into the next revision of SRP Section 19.0 and Regulatory 
Guide 1.206, ``Combined License Applications for Nuclear Power Plants 
(LWR Edition),'' June 2007.
    Disposition: On October 16, 2009, the NRC staff issued the proposed 
ISG, DC/COL-ISG-020 ``Implementation of a Seismic Margin Analysis for 
New Reactors Based on Probabilistic Risk Assessment,'' (ADAMS Accession 
No. ML092650316) to solicit public and industry comment. The NRC staff 
received comments on the proposed guidance. This final issuance 
incorporates changes from the majority of the comments. The NRC staff 
responses to these comments can be found in ADAMS Accession No. 
ML100491287.

ADDRESSES: The NRC maintains ADAMS, which provides text and image files 
of NRC's public documents. These documents may be accessed through the 
NRC's Public Electronic Reading Room on the Internet at https://www.nrc.gov/reading-rm/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 Public Document Room reference staff at 
1-800-397-4209, 301-415-4737, or by e-mail at pdr.resource@nrc.gov.

FOR FURTHER INFORMATION CONTACT: Dr. Kimberly A. Hawkins, Chief, 
Structural Engineering Branch 2, Division of Engineering, Office of the 
New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone at 301-415-0564 or e-mail at Kimberly.Hawkins@nrc.gov.

[[Page 13611]]


SUPPLEMENTARY INFORMATION: The agency posts its issued staff guidance 
in the agency external Web page (https://www.nrc.gov/reading-rm/doc-collections/isg/).

    Dated at Rockville, Maryland, this 15th day of March 2010.

    For the Nuclear Regulatory Commission.
William F. Burton,
Chief, Rulemaking and Guidance Development Branch, Division of New 
Reactor Licensing, Office of New Reactors.
[FR Doc. 2010-6200 Filed 3-19-10; 8:45 am]
BILLING CODE 7590-01-P
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