NUREG-1953, Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Surry and Peach Bottom Draft Report for Comment, 80544-80545 [2010-32140]

Download as PDF 80544 Federal Register / Vol. 75, No. 245 / Wednesday, December 22, 2010 / Notices MILLENNIUM CHALLENGE CORPORATION [MCC FR 10–16] Change of Date for December 15, 2010 Millennium Challenge Corporation Board of Directors Meeting; Sunshine Act Meeting Millennium Challenge Corporation. TIME AND DATE: 10 a.m. to 12 p.m., Wednesday, January 5, 2011. AGENCY: FOR FURTHER INFORMATION CONTACT: Information on the meeting may be obtained from Melvin Williams, Jr., Vice President, General Counsel and Corporate Secretary via e-mail at Corporatesecretary@mcc.gov or by telephone at (202) 521–3600. Background On November 23, 2010, the Millennium Challenge Corporation published a notice in the Federal Register pursuant to the Government in the Sunshine Act (5 U.S.C. 552b) stating that the MCC Board of Directors would hold a meeting December 15, 2010. (Volume 75, Number 225, page 71465) This meeting is now being moved to January 5, 2011. All other details regarding the place, status, and matters to be considered remain the same. Amendment The time and date of the meeting are amended to read: 10 a.m. to 12 p.m., Wednesday, January 5, 2011 Dated: December 20, 2010. Melvin F. Williams, Jr., VP/General Counsel and Corporate Secretary, Millennium Challenge Corporation. Specifications pertaining to the auxiliary feedwater system. The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on December 21, 2009 (74 FR 67932). However, by letter dated November 17, 2010, the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated December 15, 2009, and the licensee’s letter dated November 17, 2010, which withdrew the application for license amendment. Documents may be examined, and/or copied for a fee, at the NRC’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 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 internet at the NRC Web site, http://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 PDR Reference staff by telephone at 1–800–397–4209, or 301–415–4737 or by email to pdr.resource@nrc.gov. Dated at Rockville, Maryland, this 13th day of December 2010. For the Nuclear Regulatory Commission. John P. Boska, Senior Project Manager, Plant Licensing Branch I–1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–32138 Filed 12–21–10; 8:45 am] BILLING CODE 7590–01–P [FR Doc. 2010–32352 Filed 12–20–10; 4:15 pm] BILLING CODE 9211–03–P NUCLEAR REGULATORY COMMISSION NUCLEAR REGULATORY COMMISSION [NRC–2010–0344] [Docket No. 50–286; NRC–2010–0562] srobinson on DSKHWCL6B1PROD with NOTICES Entergy Nuclear Operations, Inc.; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (NRC, the Commission) has granted the request of Entergy Nuclear Operations, Inc. (the licensee) to withdraw its December 15, 2009, application for proposed amendment to Facility Operating License No. DPR–64 for the Indian Point Nuclear Generating Unit No. 3, located in Westchester County, New York. The proposed amendment would have revised the Technical VerDate Mar<15>2010 20:24 Dec 21, 2010 Jkt 223001 NUREG–1953, Confirmatory ThermalHydraulic Analysis To Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Surry and Peach Bottom Draft Report for Comment Nuclear Regulatory Commission. ACTION: Announcement of reopening of public comment period AGENCY: The Nuclear Regulatory Commission is re-opening the public comment period for the document entitled: NUREG–1953, ‘‘Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk SUMMARY: PO 00000 Frm 00090 Fmt 4703 Sfmt 4703 Models—Surry and Peach Bottom, Draft Report for Comment.’’ This report was originally issued for public comment via Federal Register Notice [75 FR 69140– 69141], dated November 10, 2010 (NRC– 2010–0344). DATES: Please submit comments by February 28, 2011. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. You may submit comments by any one of the following methods. Please include Docket ID NRC–2010– 0344 in the subject line of your comments. Comments submitted in writing or in electronic form will be posted on the NRC Web site and on the Federal rulemaking Web site 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 http://www.regulations.gov and search for documents filed under Docket ID NRC–2010–0344. 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 (RADB), Division of Administrative Services, Office of Administration, Mail Stop: TWB–05– B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, or by fax to RADB at 301–492– 3446. You can access publicly available documents related to this notice using the following methods: NRC’s Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available documents at the NRC’s PDR, Public File Area O1 F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. NRC’s Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available ADDRESSES: E:\FR\FM\22DEN1.SGM 22DEN1 Federal Register / Vol. 75, No. 245 / Wednesday, December 22, 2010 / Notices electronically at the NRC’s Electronic Reading Room at http://www.nrc.gov/ reading-rm/adams.html. From this page, the public can gain entry into ADAMS, which provides text and image files of NRC’s public documents. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the NRC’s PDR reference staff at 1–800–397–4209, 301–415–4737, or by e-mail to pdr.resource@nrc.gov. NUREG–1953 is available electronically under ADAMS Accession Number ML102940233. Federal Rulemaking Web site: Public comments and supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC–2010–0344. FOR FURTHER INFORMATION CONTACT: Donald Helton, Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. Telephone: 301–251–7594, e-mail: Donald.Helton@nrc.gov. SUPPLEMENTARY INFORMATION: NUREG– 1953, ‘‘Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models—Surry and Peach Bottom, Draft Report for Comment,’’ investigates specific thermal-hydraulic aspects of the Surry and Peach Bottom Standardized Plant Analysis Risk models, with the goal of further strengthening the technical basis for decisionmaking that relies on the SPAR models. This analysis employs the MELCOR computer code to analyze a number of scenarios with different assumptions. Dated at Rockville, Maryland, this 15th day of December, 2010. For the Nuclear Regulatory Commission. Kevin A. Coyne, Chief, Probabilistic Risk Assessment Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research. [FR Doc. 2010–32140 Filed 12–21–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION srobinson on DSKHWCL6B1PROD with NOTICES [Docket No. 50–261; NRC–2010–0062] Carolina Power & Light Company; H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 73.5, ‘‘Specific exemptions,’’ from the VerDate Mar<15>2010 20:24 Dec 21, 2010 Jkt 223001 implementation date for certain new requirements of 10 CFR Part 73, ‘‘Physical protection of plants and materials,’’ for Facility Operating License No. DPR–23, issued to Carolina Power & Light Company (the licensee), for operation of the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP), located in Darlington County, South Carolina. In accordance with 10 CFR 51.21, ‘‘Criteria for and identification of licensing and regulatory actions requiring environmental assessments,’’ the NRC staff prepared an environmental assessment documenting its finding. The NRC staff concluded that the proposed action will have no significant environmental impact. Environmental Assessment Identification of the Proposed Action The proposed action would exempt the licensee from the required implementation date of March 31, 2010, for one specific requirement of 10 CFR Part 73. Specifically, HBRSEP would be granted a second exemption, further extending the date for full compliance with one remaining item of the requirements contained in 10 CFR 73.55, from December 30, 2010, (the date specified in a prior exemption granted by NRC on March 3, 2010), until September 16, 2011. The proposed action, an extension of the schedule for completion of certain actions required by the revised 10 CFR Part 73, does not result in any additional physical changes to the reactor, fuel, plant structures, support structures, water, or land at the HBRSEP site. The proposed action is in accordance with the licensee’s application dated September 30, 2010. The Need for the Proposed Action The proposed exemption is needed to provide the licensee with additional time, beyond the date granted by the NRC letter dated March 3, 2010, to implement one remaining item of the two requirements in the previous exemption that involves important physical modifications to the HBRSEP security system. The licensee has performed an extensive evaluation of the revised 10 CFR Part 73 and has achieved compliance with a vast majority of the revised rule by the March 31, 2010, compliance date. However, the licensee has determined that implementation of one specific provisions of the rule will require more time to implement because they involve upgrades to the security system that require significant physical modifications (e.g., the relocation of certain security assets to a new security PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 80545 building that will be constructed, and the addition of certain power supplies). There are several issues which have delayed the work to this point and impacted the projected schedule: (1) The complexity of the design and construction of the projects which lead to unforeseen scope growth; (2) a better understanding of the time necessary for transition and testing for the new systems; and (3) due to a fire in an electrical switchgear room, the spring refueling outage was extended beyond that originally anticipated when schedules were first developed. These issues were revealed as the design evolved from the conceptual state to a detailed design. Additional time, beyond that previously approved, is needed due the extensive redesign and review effort that was unforeseen at the conceptual design stage. Environmental Impacts of the Proposed Action The NRC staff has completed its environmental assessment of the proposed exemption and has concluded that the proposed action to extend the implementation deadline would not significantly affect plant safety and would not have a significant adverse effect on the probability or consequences of an accident. The proposed action would not result in an increased radiological hazard beyond those previously analyzed in the environmental assessment and finding of no significant impact made by the Commission in promulgating its revisions to 10 CFR Part 73 as discussed in a Federal Register notice dated March 27, 2009 (74 FR 13967). There will be no change to radioactive effluents that affect radiation exposures to plant workers and members of the public. Therefore, no changes or different types of radiological impacts are expected as a result of the proposed exemption. The proposed action does not result in changes to land use or water use, or result in changes to the quality or quantity of non-radiological effluents. No changes to the National Pollution Discharge Elimination System permit are needed. No effects on the aquatic or terrestrial habitat in the vicinity of the plant, or to threatened, endangered, or protected species under the Endangered Species Act, or impacts to essential fish habitat covered by the MagnusonStevens Act are expected. There are no impacts to the air or ambient air quality. There are no impacts to historical and cultural resources. There would be no impact to socioeconomic resources. Therefore, no changes to or different types of non-radiological environmental E:\FR\FM\22DEN1.SGM 22DEN1

Agencies

[Federal Register Volume 75, Number 245 (Wednesday, December 22, 2010)]
[Notices]
[Pages 80544-80545]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-32140]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2010-0344]


NUREG-1953, Confirmatory Thermal-Hydraulic Analysis To Support 
Specific Success Criteria in the Standardized Plant Analysis Risk 
Models--Surry and Peach Bottom Draft Report for Comment

AGENCY: Nuclear Regulatory Commission.

ACTION: Announcement of reopening of public comment period

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

SUMMARY: The Nuclear Regulatory Commission is re-opening the public 
comment period for the document entitled: NUREG-1953, ``Confirmatory 
Thermal-Hydraulic Analysis to Support Specific Success Criteria in the 
Standardized Plant Analysis Risk Models--Surry and Peach Bottom, Draft 
Report for Comment.'' This report was originally issued for public 
comment via Federal Register Notice [75 FR 69140-69141], dated November 
10, 2010 (NRC-2010-0344).

DATES: Please submit comments by February 28, 2011. Comments received 
after this date will be considered if it is practical to do so, but the 
NRC staff is able to ensure consideration only for comments received on 
or before this date.

ADDRESSES: You may submit comments by any one of the following methods. 
Please include Docket ID NRC-2010-0344 in the subject line of your 
comments. Comments submitted in writing or in electronic form will be 
posted on the NRC Web site and on the Federal rulemaking Web site 
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 http://www.regulations.gov and 
search for documents filed under Docket ID NRC-2010-0344. 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 (RADB), Division of Administrative Services, Office 
of Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, or by fax to RADB at 301-492-
3446.
    You can access publicly available documents related to this notice 
using the following methods:
    NRC's Public Document Room (PDR): The public may examine and have 
copied, for a fee, publicly available documents at the NRC's PDR, 
Public File Area O1 F21, One White Flint North, 11555 Rockville Pike, 
Rockville, Maryland.
    NRC's Agencywide Documents Access and Management System (ADAMS): 
Publicly available documents created or received at the NRC are 
available

[[Page 80545]]

electronically at the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain 
entry into ADAMS, which provides text and image files of NRC's public 
documents. If you do not have access to ADAMS or if there are problems 
in accessing the documents located in ADAMS, contact the NRC's PDR 
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to 
pdr.resource@nrc.gov. NUREG-1953 is available electronically under 
ADAMS Accession Number ML102940233.
    Federal Rulemaking Web site: Public comments and supporting 
materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC-2010-0344.

FOR FURTHER INFORMATION CONTACT: Donald Helton, Division of Risk 
Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001. Telephone: 301-251-
7594, e-mail: Donald.Helton@nrc.gov.

SUPPLEMENTARY INFORMATION: NUREG-1953, ``Confirmatory Thermal-Hydraulic 
Analysis to Support Specific Success Criteria in the Standardized Plant 
Analysis Risk Models--Surry and Peach Bottom, Draft Report for 
Comment,'' investigates specific thermal-hydraulic aspects of the Surry 
and Peach Bottom Standardized Plant Analysis Risk models, with the goal 
of further strengthening the technical basis for decisionmaking that 
relies on the SPAR models. This analysis employs the MELCOR computer 
code to analyze a number of scenarios with different assumptions.

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

    For the Nuclear Regulatory Commission.
Kevin A. Coyne,
Chief, Probabilistic Risk Assessment Branch, Division of Risk Analysis, 
Office of Nuclear Regulatory Research.
[FR Doc. 2010-32140 Filed 12-21-10; 8:45 am]
BILLING CODE 7590-01-P