Notice of Issuance of Regulatory Guide, 40943-40944 [2011-17441]

Download as PDF Federal Register / Vol. 76, No. 133 / Tuesday, July 12, 2011 / Notices the NRC staff’s original proposed no significant hazards determination. The Commission’s related evaluation of the amendment is contained in a Safety Evaluation dated June 28, 2011. No significant hazards consideration comments received: No. emcdonald on DSK2BSOYB1PROD with NOTICES Florida Power and Light Company, Docket Nos. 50–250 and 50–251, Turkey Point Plant, Units 3 and 4, Miami-Dade County, Florida Date of application for amendments: June 25, 2009, as supplemented by letters dated July 21, July 30, August 26, 2009, February 10, March 15, April 14, April 28, May 21, June 11, June 23, June 25, September 2, September 15, October 13, December 14, 2010, and May 11, 2011. Brief description of amendments: The amendments revised the licensing bases to adopt the alternative source term as allowed in Title 10 of the Code of Federal Regulations (10 CFR) 50.67. Date of issuance: June 23, 2011. Effective date: As of the date of issuance and shall be implemented by the completion of the Cycle 26 refueling outage for Unit 3 and Cycle 27 refueling outage for Unit 4. Amendment Nos.: Unit 3–244 and Unit 4–240. Renewed Facility Operating License Nos. DPR–31 and DPR–41: Amendments revised the Operating Licenses and the Technical Specifications. Date of initial notice in Federal Register: December 29, 2009 (74 FR 68870). The supplements dated July 21, July 30, August 26, 2009, February 10, March 15, April 14, April 28, June 11, June 23, June 25, September 2, September 15, October 13, December 14, 2010, and May 11, 2011, 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 as published in the Federal Register. The supplement dated May 21, 2010, changed the scope of the application as originally noticed. Due to the changes, the application was renoticed and published in the Federal Register on July 13, 2010 (75 FR 39978). The Commission’s related evaluation of the amendments is contained in a Safety Evaluation dated June 23, 2011. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 30th day of June 2011. VerDate Mar<15>2010 16:14 Jul 11, 2011 Jkt 223001 For the Nuclear Regulatory Commission. Allen G. Howe, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2011–17439 Filed 7–11–11; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0216] Notice of Issuance of Regulatory Guide Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.152, Revision 3, ‘‘Criteria for Use of Computers in Safety Systems of Nuclear Power Plants.’’ AGENCY: FOR FURTHER INFORMATION CONTACT: Mark P. Orr, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–251– 7495 or e-mail: Mark.Orr@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to an existing 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 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. Revision 3 of Regulatory Guide 1.152, ‘‘Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,’’ was issued with a temporary identification as Draft Regulatory Guide, DG–1249, for public comments on June 22, 2010 (75 FR 35508). The public comment period closed on August 20, 2010. All comments that were received were considered and, where appropriate, the final guide was revised to address the comments. Editorial changes and clarifications were made to Regulatory Guide 1.152 as a result of the public comments. These include minor changes to the discussion section to improve consistency with other NRC regulations and guidance, clarification of the regulatory criteria to more clearly indicate that licensees are responsible for demonstrating establishment of a PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 40943 secure development and operational environment, and clarification of regulatory criteria to precisely state the expectations of actions taken to protect developmental activities. This guide describes a method that the staff of the NRC considers acceptable to implement Title 10, of the Code of Federal Regulations, part 50, ‘‘Domestic Licensing of Production and Utilization Facilities’’ (10 CFR part 50); 10 CFR 50.55a(h); General Design Criterion (GDC) 21, ‘‘Protection System Reliability and Testability,’’ of Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ to 10 CFR part 50; and Criterion III, ‘‘Design Control,’’ of Appendix B, ‘‘Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,’’ to 10 CFR part 50 with regard to the use of computers in safety systems of nuclear power plants. This guide applies to all types of commercial nuclear power plants. Regulatory Guide 1.152 was not uniquely developed for non-power reactors; therefore, the applicability of this guide for those facilities should be determined on a case-by-case basis. This regulatory guide describes a method that the NRC staff deems acceptable for complying with the Commission’s regulations for promoting high functional reliability, design quality, and a secure development and operational environment for the use of digital computers in the safety systems of nuclear power plants. In this context, the term ‘‘computer’’ identifies a system that includes computer hardware, software, firmware, and interfaces. II. Further Information Electronic copies of Regulatory Guide 1.152, Revision 3 are available through the NRC’s public Web site under ‘‘Regulatory Guides’’ at http:// www.nrc.gov/reading-rm/doccollections/. The regulatory analysis may be found through the NRC’s Agencywide Documents Access and Management System (ADAMS) under Accession No. ML101320317. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR) located at Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. 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 800–397–4209, by fax at 301–415–3548, and by e-mail to pdr.resources@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. E:\FR\FM\12JYN1.SGM 12JYN1 40944 Federal Register / Vol. 76, No. 133 / Tuesday, July 12, 2011 / Notices Dated at Rockville, Maryland, this 5th day of July, 2011. For the Nuclear Regulatory Commission. Harriet Karagiannis, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2011–17441 Filed 7–11–11; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2011–0006] Sunshine Federal Register Notice Nuclear Regulatory Commission. DATE: Weeks of July 11, 18, 25, August 1, 8, 15, 2011. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. AGENCY HOLDING THE MEETINGS: Week of July 11, 2011 Tuesday, July 12, 2011 9:30 a.m. Briefing on the NRC Actions for Addressing the Integrated Regulatory Review Service (IRRS) Report (Public Meeting (Contact: Jon Hopkins, 301–415–3027). This meeting will be webcast live at the Web address—http://www.nrc.gov. Week of July 18, 2011—Tentative Tuesday, July 19, 2011 9:30 a.m. Briefing on the Task Force Review of NRC Processes and Regulations Following Events in Japan (Public Meeting) (Contact: Nathan Sanfilippo, 301–415–3951). This meeting will be webcast live at the Web address—http://www.nrc.gov. Week of July 25, 2011—Tentative Dated: July 7, 2011. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. [FR Doc. 2011–17574 Filed 7–8–11; 11:15 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Thursday, July 28, 2011 emcdonald on DSK2BSOYB1PROD with NOTICES Week of August 15, 2011—Tentative There are no meetings scheduled for the week of August 15, 2011. * * * * * * The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—(301) 415–1292. Contact person for more information: Rochelle Bavol, (301) 415–1651. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: http://www.nrc.gov/public-involve/ public-meetings/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 Bill Dosch, Chief, Work Life and Benefits Branch, at 301–415–6200, TDD: 301– 415–2100, or by e-mail at william.dosch@nrc.gov. Determinations on requests for reasonable accommodation will be made on a caseby-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. 9 a.m. Briefing on Severe Accidents and Options for Proceeding with Level 3 Probabilistic Risk Assessment Activities (Public Meeting) (Contact: Daniel Hudson, 301–251– 7919). This meeting will be webcast live at the Web address—http://www.nrc.gov. [Docket Nos. 50–272 and 50–311; NRC– 2009–0390] Week of August 1, 2011—Tentative Notice is hereby given that the U.S. Nuclear Regulatory Commission (the Commission) has issued Renewed Facility Operating License Nos. DPR–70 and DPR–75 to PSEG Nuclear LLC (the licensee), the operator of the Salem Nuclear Generating Station, Units 1 and There are no meetings scheduled for the week of August 1, 2011. Week of August 8, 2011—Tentative There are no meetings scheduled for the week of August 8, 2011. VerDate Mar<15>2010 16:14 Jul 11, 2011 Jkt 223001 PSEG Nuclear, LLC, Salem Nuclear Generating Station, Units 1 and 2; Notice of Issuance of Renewed Facility Operating License Nos. DPR–70 and DPR–75 for an Additional 20-Year Period PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 2 (Salem). Renewed Facility Operating License Nos. DPR–70 and DPR–75 authorize the licensee to operate Salem at reactor core power levels not in excess of 3,459 megawatts thermal in accordance with the provisions of the Salem renewed license and its technical specifications. The notice also serves as the record of decision for the renewal of Facility Operating License Nos. DPR–70 and DPR–75, consistent with Title 10 of the Code of Federal Regulations (10 CFR) 51.103, ‘‘Record of Decision—General.’’ As discussed in the final supplemental environmental impact statement for Salem (NUREG–1437, Supplement 45, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 45, Regarding Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2, Final Report,’’ issued March 2011), the Commission has considered a range of reasonable alternatives that included generation from coal-fired generation, natural gas combined-cycle generation, a combined alternative, and the no-action alternative. The factors considered in the record of decision can be found in the supplemental environmental impact statement for Salem. Salem’s units are pressurized-water reactors located in Lower Alloways Creek Township, Salem County, NJ. The application for the renewed license complied with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s regulations. As required by the Act and the Commission’s regulations in 10 CFR Chapter I, ‘‘Nuclear Regulatory Commission,’’ the Commission has made appropriate findings, which are set forth in the license. Prior public notice of the action involving the proposed issuance of the renewed license and of an opportunity for a hearing regarding the proposed issuance of the renewed license was published in the Federal Register on October 23, 2009 (74 FR 54854). For further details with respect to this action, see (1) PSEG Nuclear LLC’s license renewal application for Salem Nuclear Generating Station, Units 1 and 2, dated August 18, 2009, as supplemented by letters dated through May 18, 2011, (2) the Commission’s safety evaluation report (NUREG–2101, ‘‘Safety Evaluation Report Related to the License Renewal of the Salem Nuclear Generating Station,’’ issued June 2011), (3) the licensee’s updated safety analysis report, and (4) the Commission’s final environmental impact statement (NUREG–1437, Supplement 45), for Salem, published in March 2011. These E:\FR\FM\12JYN1.SGM 12JYN1

Agencies

[Federal Register Volume 76, Number 133 (Tuesday, July 12, 2011)]
[Notices]
[Pages 40943-40944]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-17441]


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NUCLEAR REGULATORY COMMISSION

[NRC-2010-0216]


Notice of Issuance of Regulatory Guide

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Regulatory Guide 1.152, 
Revision 3, ``Criteria for Use of Computers in Safety Systems of 
Nuclear Power Plants.''

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

FOR FURTHER INFORMATION CONTACT: Mark P. Orr, Regulatory Guide 
Development Branch, Division of Engineering, Office of Nuclear 
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone: 301-251-7495 or e-mail: Mark.Orr@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision 
to an existing 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 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.
    Revision 3 of Regulatory Guide 1.152, ``Criteria for Use of 
Computers in Safety Systems of Nuclear Power Plants,'' was issued with 
a temporary identification as Draft Regulatory Guide, DG-1249, for 
public comments on June 22, 2010 (75 FR 35508). The public comment 
period closed on August 20, 2010. All comments that were received were 
considered and, where appropriate, the final guide was revised to 
address the comments. Editorial changes and clarifications were made to 
Regulatory Guide 1.152 as a result of the public comments. These 
include minor changes to the discussion section to improve consistency 
with other NRC regulations and guidance, clarification of the 
regulatory criteria to more clearly indicate that licensees are 
responsible for demonstrating establishment of a secure development and 
operational environment, and clarification of regulatory criteria to 
precisely state the expectations of actions taken to protect 
developmental activities. This guide describes a method that the staff 
of the NRC considers acceptable to implement Title 10, of the Code of 
Federal Regulations, part 50, ``Domestic Licensing of Production and 
Utilization Facilities'' (10 CFR part 50); 10 CFR 50.55a(h); General 
Design Criterion (GDC) 21, ``Protection System Reliability and 
Testability,'' of Appendix A, ``General Design Criteria for Nuclear 
Power Plants,'' to 10 CFR part 50; and Criterion III, ``Design 
Control,'' of Appendix B, ``Quality Assurance Criteria for Nuclear 
Power Plants and Fuel Reprocessing Plants,'' to 10 CFR part 50 with 
regard to the use of computers in safety systems of nuclear power 
plants. This guide applies to all types of commercial nuclear power 
plants. Regulatory Guide 1.152 was not uniquely developed for non-power 
reactors; therefore, the applicability of this guide for those 
facilities should be determined on a case-by-case basis.
    This regulatory guide describes a method that the NRC staff deems 
acceptable for complying with the Commission's regulations for 
promoting high functional reliability, design quality, and a secure 
development and operational environment for the use of digital 
computers in the safety systems of nuclear power plants. In this 
context, the term ``computer'' identifies a system that includes 
computer hardware, software, firmware, and interfaces.

II. Further Information

    Electronic copies of Regulatory Guide 1.152, Revision 3 are 
available through the NRC's public Web site under ``Regulatory Guides'' 
at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory 
analysis may be found through the NRC's Agencywide Documents Access and 
Management System (ADAMS) under Accession No. ML101320317.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR) located at Room O-1F21, One White 
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-2738. 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 800-397-4209, by 
fax at 301-415-3548, and by e-mail to pdr.resources@nrc.gov.
    Regulatory guides are not copyrighted, and NRC approval is not 
required to reproduce them.


[[Page 40944]]


    Dated at Rockville, Maryland, this 5th day of July, 2011.

    For the Nuclear Regulatory Commission.
Harriet Karagiannis,
 Acting Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2011-17441 Filed 7-11-11; 8:45 am]
BILLING CODE 7590-01-P