Final Regulatory Guide: Issuance, Availability, 48381-48382 [2010-19676]

Download as PDF Federal Register / Vol. 75, No. 153 / Tuesday, August 10, 2010 / Notices NSHC determination, any such hearing would take place after issuance of the amendment. The Commission’s related evaluation of the requested amendment, state consultation, and final NSHC determination are contained in a safety evaluation dated June 25, 2010. The NRC staff prepared an environmental assessment (75 FR 36446) and determined that the requested amendment will not have a significant effect on the quality of the human environment. Attorney for licensee: M. Stanford Blanton, Balch & Bingham, LLP. NRC Branch Chief: Jeffrey Cruz. sroberts on DSKB9S0YB1PROD with NOTICES Wolf Creek Nuclear Operating Corporation, Docket No. 50–482, Wolf Creek Generating Station, Coffey County, Kansas Date of amendment request: October 10, 2010, as supplemented by letter dated March 8, 2010. Brief description of amendment: The amendment revised Technical Specification (TS) 3.1.7, ‘‘Rod Position Indication,’’ TS 3.2.1, ‘‘Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology),’’ TS 3.2.2, ‘‘Nuclear Enthalpy Rise Hot Channel Factor (FNDH),’’ TS 3.2.4, ‘‘Quadrant Power Tilt Ratio (QPTR),’’ and TS 3.3.1, ‘‘Reactor Trip System (RTS) Instrumentation,’’ for use of the Best Estimate Analyzer for Core Operations—Nuclear (BEACON) Power Distribution Monitoring System (PDMS), as described in WCAP–12472– P–A, ‘‘BEACON Core Monitoring and Operations Support System,’’ to perform power distribution surveillances. Date of issuance: July 23, 2010. Effective date: As the date of issuance and shall be implemented by December 29, 2010. Amendment No.: 188. Renewed Facility Operating License No. NPF–42. The amendment revised the Operating License and Technical Specifications. Date of initial notice in Federal Register: January 26, 2010 (75 FR 4120). The supplemental letter dated March 8, 2010, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff’s original proposed no significant hazards consideration determination. The Commission’s related evaluation of the amendment is contained in a Safety Evaluation dated July 23, 2010. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 30th day of July, 2010. VerDate Mar<15>2010 16:26 Aug 09, 2010 Jkt 220001 For The Nuclear Regulatory Commission. Robert A. Nelson, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–19678 Filed 8–9–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0002] Sunshine Federal Register Notice Nuclear Regulatory Commission. DATE: Weeks of August 9, 16, 23, 30, and September 6, 13, 2010. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and closed. AGENCY HOLDING THE MEETINGS: Week of August 9, 2010 Thursday, August 12, 2010 9:25 a.m. Affirmation Session (Public Meeting) (Tentative). a. U.S. Army Installation Command (Schofield Barracks, Oahu, Hawaii, and Pohakuloa Training Area, Island of Hawaii, Hawaii), Appeal of Isaac D. Harp (Tentative). This meeting will be Webcast live at the Web address—https://www.nrc.gov. 9:30 a.m. Meeting with Organization of Agreement States (OAS) and Conference of Radiation Control Program Directors (CRCPD) (Public Meeting) (Contact: Cindy Flannery, 301–415–0223). This meeting will be Webcast live at the Web address—https://www.nrc.gov. Week of August 16, 2010—Tentative There are no meetings scheduled for the week of August 16, 2010. Week of August 23, 2010—Tentative There are no meetings scheduled for the week of August 23, 2010. Week of August 30, 2010—Tentative There are no meetings scheduled for the week of August 30, 2010. Week of September 6, 2010—Tentative There are no meetings scheduled for the week of September 6, 2010. Week of September 13, 2010—Tentative There are no meetings scheduled for the week of September 13, 2010. * The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—(301) 415–1292. PO 00000 Frm 00080 Fmt 4703 Sfmt 4703 48381 Contact person for more information: Rochelle Bavol, (301) 415–1651. The NRC Commission Meeting Schedule can be found on the Internet at: https://www.nrc.gov/about-nrc/policymaking/schedule.html. The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify Angela Bolduc, Chief, Employee/Labor Relations and Work Life Branch, at 301– 492–2230, TDD: 301–415–2100, or by email at angela.bolduc@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. This notice is distributed electronically to subscribers. If you no longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301–415–1969), or send an e-mail to darlene.wright@nrc.gov. Dated: August 5, 2010. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. [FR Doc. 2010–19806 Filed 8–6–10; 4:15 pm] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0274] Final Regulatory Guide: Issuance, Availability Nuclear Regulatory Commission. ACTION: Notice of issuance and availability of Regulatory Guide, RG 1.216, ‘‘Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure.’’ AGENCY: FOR FURTHER INFORMATION CONTACT: Robert G. Roche, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: (301) 251– 7645 or e-mail Robert.Roche@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC or Commission) is issuing a new guide in the agency’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information such as methods that are acceptable to the NRC staff for implementing specific E:\FR\FM\10AUN1.SGM 10AUN1 48382 Federal Register / Vol. 75, No. 153 / Tuesday, August 10, 2010 / Notices sroberts on DSKB9S0YB1PROD with NOTICES parts of the agency’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. Regulatory Guide 1.216, ‘‘Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure,’’ was issued with a temporary identification as Draft Regulatory Guide, DG–1203. This guide describes methods that the NRC staff considers acceptable for (1) predicting the internal pressure capacity for containment structures above the design-basis accident pressure, (2) demonstrating containment structural integrity related to combustible gas control, and (3) demonstrating containment structural integrity to meet the Commission’s performance goals related to the prevention and mitigation of severe accidents. It provides guidance on methods for satisfying requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, ‘‘Licenses, Certifications, and Approvals for Nuclear Power Plants.’’ Requirements in 10 CFR 52.47, ‘‘Contents of Applications; Technical Information,’’ and in 10 CFR 52.79, ‘‘Contents of Applications; Technical Information in Final Safety Analysis Report [FSAR],’’ relate to the structural integrity of containments under internal pressurization that pertain to the containment structural capacity above design-basis pressures, to combustible gas control, and to the prevention and mitigation of severe accidents. This guidance is intended to be consistent with the Commission’s goals and other related guidance, as discussed in the remainder of this section. This regulatory guide does not address requirements and guidance for the structural evaluation of containments for design-basis pressure. II. Further Information In December 2008, DG–1203 was published with a public comment period of 60 days from the issuance of the guide. The public comment period closed on February 9, 2009. The staff’s responses to the public comments received are located in the NRC’s Agencywide Documents Access and Management System under Accession Number ML092800554. The regulatory analysis may be found in ADAMS under Accession No. ML101890047. Electronic copies of RG 1.216 are available through the NRC’s public Web site under ‘‘Regulatory Guides’’ at https:// www.nrc.gov/reading-rm/doccollections/. VerDate Mar<15>2010 16:26 Aug 09, 2010 Jkt 220001 In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR) 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.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. dated January 1999. This guide provides general procedures for the preparation of license termination plans for nuclear power reactors. Use of this regulatory guide will help to ensure the completeness of the information provided in a license termination plan, assist the staff of the NRC and others in locating pertinent information, and facilitate the review process. However, the NRC does not require conformance with the procedures, which are provided for guidance only. Dated at Rockville, Maryland, this 3rd day of August, 2010. For the Nuclear Regulatory Commission. Harriet Karagiannis, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. II. Further Information [FR Doc. 2010–19676 Filed 8–9–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0275] Draft Regulatory Guide: Issuance, Availability Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, DG–1228, ‘‘Standard Format and Content of License Termination Plans for Nuclear Power Reactors.’’ AGENCY: FOR FURTHER INFORMATION CONTACT: James C. Shepherd, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: (301) 415– 6712 or e-mail James.Shepherd@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the agency’s ‘‘Regulatory Guide’’ series. This series was 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. The draft regulatory guide (DG) is temporarily identified by its task number, DG–1228, which should be mentioned in all related correspondence. DG–1228 is proposed Revision 1 of Regulatory Guide 1.179, PO 00000 Frm 00081 Fmt 4703 Sfmt 4703 The NRC staff is soliciting comments on DG–1228. Comments may be accompanied by relevant information or supporting data and should mention DG–1228 in the subject line. Comments submitted in writing or in electronic form will be made available to the public in their entirety through the NRC’s Agencywide Documents Access and Management System (ADAMS). ADDRESSES: You may submit comments by any one of the following methods. Please include Docket ID NRC–2010–0275 in the subject line of your comments. Comments submitted in writing or in electronic form will be posted on the NRC website and on the Federal rulemaking website Regulations.gov. Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed. The NRC requests that any party soliciting or aggregating comments received from other persons for submission to the NRC inform those persons that the NRC will not edit their comments to remove any identifying or contact information, and therefore, they should not include any information in their comments that they do not want publicly disclosed. Federal Rulemaking Web site: Go to https://www.regulations.gov and search for documents filed under Docket ID NRC–2010–0275. Address questions about NRC dockets to Carol Gallagher 301–492–3668; e-mail Carol.Gallagher@nrc.gov. Mail comments to: Cindy Bladey, Chief, Rules, Announcements, and Directives Branch (RAD), Office of Administration, Mail Stop: TWB–05– B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, or by fax to RDB at (301) 492– 3446. You can access publicly available documents related to this notice using the following methods: E:\FR\FM\10AUN1.SGM 10AUN1

Agencies

[Federal Register Volume 75, Number 153 (Tuesday, August 10, 2010)]
[Notices]
[Pages 48381-48382]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-19676]


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NUCLEAR REGULATORY COMMISSION

[NRC-2010-0274]


Final Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of issuance and availability of Regulatory Guide, RG 
1.216, ``Containment Structural Integrity Evaluation for Internal 
Pressure Loadings Above Design-Basis Pressure.''

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

FOR FURTHER INFORMATION CONTACT: Robert G. Roche, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 251-
7645 or e-mail Robert.Roche@nrc.gov.

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC or Commission) is 
issuing a new guide in the agency's ``Regulatory Guide'' series. This 
series was developed to describe and make available to the public 
information such as methods that are acceptable to the NRC staff for 
implementing specific

[[Page 48382]]

parts of the agency'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.
    Regulatory Guide 1.216, ``Containment Structural Integrity 
Evaluation for Internal Pressure Loadings Above Design-Basis 
Pressure,'' was issued with a temporary identification as Draft 
Regulatory Guide, DG-1203. This guide describes methods that the NRC 
staff considers acceptable for (1) predicting the internal pressure 
capacity for containment structures above the design-basis accident 
pressure, (2) demonstrating containment structural integrity related to 
combustible gas control, and (3) demonstrating containment structural 
integrity to meet the Commission's performance goals related to the 
prevention and mitigation of severe accidents. It provides guidance on 
methods for satisfying requirements in Title 10 of the Code of Federal 
Regulations (10 CFR) Part 52, ``Licenses, Certifications, and Approvals 
for Nuclear Power Plants.'' Requirements in 10 CFR 52.47, ``Contents of 
Applications; Technical Information,'' and in 10 CFR 52.79, ``Contents 
of Applications; Technical Information in Final Safety Analysis Report 
[FSAR],'' relate to the structural integrity of containments under 
internal pressurization that pertain to the containment structural 
capacity above design-basis pressures, to combustible gas control, and 
to the prevention and mitigation of severe accidents. This guidance is 
intended to be consistent with the Commission's goals and other related 
guidance, as discussed in the remainder of this section. This 
regulatory guide does not address requirements and guidance for the 
structural evaluation of containments for design-basis pressure.

II. Further Information

    In December 2008, DG-1203 was published with a public comment 
period of 60 days from the issuance of the guide. The public comment 
period closed on February 9, 2009. The staff's responses to the public 
comments received are located in the NRC's Agencywide Documents Access 
and Management System under Accession Number ML092800554. The 
regulatory analysis may be found in ADAMS under Accession No. 
ML101890047. Electronic copies of RG 1.216 are available through the 
NRC's public Web site under ``Regulatory Guides'' at https://www.nrc.gov/reading-rm/doc-collections/.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR) 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.resource@nrc.gov.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 3rd day of August, 2010.

    For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2010-19676 Filed 8-9-10; 8:45 am]
BILLING CODE 7590-01-P