Application for a License To Export Major Components for Nuclear Reactors, 35167-35168 [E8-14002]

Download as PDF Federal Register / Vol. 73, No. 120 / Friday, June 20, 2008 / Notices not considered production of an article within the meaning of Section 222 of the Trade Act of 1974. The allegation of a shift to another country might be relevant if it was determined that workers of the subject firm produced an article. Since the investigation determined that workers of JP Morgan Chase & Co., JP Morgan Asset Management, Fiduciary Administration—Court Accounting, Troy, Michigan do not produce an article, there cannot be imports nor a shift in production of an ‘‘article’’ abroad within the meaning of the Trade Act of 1974 in this instance. The petitioner did not supply facts not previously considered; nor provide additional documentation indicating that there was either (1) a mistake in the determination of facts not previously considered or (2) a misinterpretation of facts or of the law justifying reconsideration of the initial determination. After careful review of the request for reconsideration, the Department determines that 29 CFR 90.18(c) has not been met. Conclusion After review of the application and investigative findings, I conclude that there has been no error or misinterpretation of the law or of the facts which would justify reconsideration of the Department of Labor’s prior decision. Accordingly, the application is denied. Signed in Washington, DC, this 9th day of June 2008. Elliott S. Kushner, Certifying Officer, Division of Trade Adjustment Assistance. [FR Doc. E8–13977 Filed 6–19–08; 8:45 am] apply for worker adjustment assistance and alternative trade adjustment assistance under amended petition number TA–W–61,265, which does not expire until May 16, 2009. Consequently, further investigation in this case would serve no purpose and the investigation has been terminated. Signed at Washington, DC, this 13th day of June 2008. Linda G. Poole, Certifying Officer, Division of Trade Adjustment Assistance. [FR Doc. E8–13971 Filed 6–19–08; 8:45 am] Application for a License To Export Major Components for Nuclear Reactors Employment and Training Administration [TA–W–63,417] Greene Plastics Corporation, Hope Valley, RI; Notice of Termination of Investigation Pursuant to Section 221 of the Trade Act of 1974, as amended, an investigation was initiated on May 21, 2008 in response to a petition filed by a company official on behalf of workers of Greene Plastics Corporation, Hope Valley, Rhode Island. The petitioner has requested that the petition be withdrawn. Consequently, the investigation has been terminated. Signed in Washington, DC, this 9th day of June 2008. Linda G. Poole, Certifying Officer, Division of Trade Adjustment Assistance. [FR Doc. E8–13979 Filed 6–19–08; 8:45 am] BILLING CODE 4510–FN–P [TA–W–63,463 jlentini on PROD1PC65 with NOTICES Grapevine Staffing, LLC, Workers OnSite at O’Bryan Brothers Incorporated, Leon, IA; Notice of Termination of Investigation Pursuant to Section 221 of the Trade Act of 1974, as amended, an investigation was initiated on June 5, 2008, in response to a petition filed by a State agency representative on behalf of workers of Grapevine Staffing, LLC, working on-site at O’Bryan Brothers Incorporated, Leon, Iowa. The petitioning worker group is covered by a certification of eligibility to VerDate Aug<31>2005 16:53 Jun 19, 2008 Jkt 214001 BILLING CODE 4510–FN–P DEPARTMENT OF LABOR Employment and Training Administration [TA–W–63,486] Signed at Washington, DC, this 11th day of June 2008. Richard Church, Certifying Officer, Division of Trade Adjustment Assistance. [FR Doc. E8–13980 Filed 6–19–08; 8:45 am] NUCLEAR REGULATORY COMMISSION DEPARTMENT OF LABOR Employment and Training Administration W–63,301) which expires on May 16, 2010. Consequently, further investigation in this case would serve no purpose, and the investigation has been terminated. BILLING CODE 4510–FN–P BILLING CODE 4510–FN–P DEPARTMENT OF LABOR 35167 Sun Chemical Company, North Haven, CT; Notice of Termination of Investigation Pursuant to Section 221 of the Trade Act of 1974, as amended, an investigation was initiated on June 3, 2008, in response to a worker petition filed by a state workforce official on behalf of workers of Sun Chemical Company employed on-site at the North Haven, Connecticut location of Quebecor World Northeast Graphics, Inc. The petitioning group of workers is covered by an active certification, (TA– PO 00000 Frm 00052 Fmt 4703 Sfmt 4703 Pursuant to 10 CFR 110.70 (b)(1) ‘‘Public Notice of Receipt of an Application,’’ please take notice that the Nuclear Regulatory Commission (NRC) has received the following request for an export license. Copies of the request are available electronically through ADAMS and can be accessed through the Public Electronic Reading Room (PERR) link http://www.nrc.gov/reading-rm.html at the NRC Homepage. A request for a hearing or petition for leave to intervene may be filed within thirty days after publication of this notice in the Federal Register. Any request for hearing or petition for leave to intervene shall be served by the requestor or petitioner upon the applicant, the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555; the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555; and the Executive Secretary, U.S. Department of State, Washington, DC 20520. A request for a hearing or petition for leave to intervene may be filed with the NRC electronically in accordance with NRC’s E-Filing rule promulgated in August 2007, 72 FR 49139 (Aug. 28, 2007). Information about filing electronically is available on the NRC’s public Web site at http://www.nrc.gov/ site-help/e-submittals.html. To ensure timely electronic filing, at least five days prior to the filing deadline, the petitioner/requestor should contact the Office of the Secretary by e-mail at HEARINGDOCKET@NRC.GOV, or by calling (301) 415–1677, to request a digital ID certificate and allow for the creation of an electronic docket. In addition to a request for hearing or petition for leave to intervene, written comments, in accordance with 10 CFR 110.81 should be submitted within thirty days after publication of this E:\FR\FM\20JNN1.SGM 20JNN1 35168 Federal Register / Vol. 73, No. 120 / Friday, June 20, 2008 / Notices notice in the Federal Register to Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Rulemaking and Adjudications. In its review of applications for licenses and license amendments involving exports of major components of a utilization facility as defined in 10 CFR Part 110 and noticed herein, the Commission does not evaluate the health, safety or environmental effects in the recipient nation of the facility or facilities to be exported. The information concerning this license application follows: NRC APPLICATION FOR LICENSE TO EXPORT MAJOR COMPONENTS OF A NUCLEAR UTILIZATION FACILITY Name of applicant, date of application, date received, application No., docket No. Total quantity/ description of major components End use Curtiss-Wright Electro-Mechanical Corporation, May 14, 2008, May 15, 2008, XR172, 11005752. As specified in 10 CFR Part 110, Appendix A Items (4) and (9), one (1) complete primary reactor coolant pump (RCP) or major sub-assemblies thereof, and various raw materials and parts/components to be processed into finished parts, components, sub-assemblies and assemblies in the People’s Republic of China for return to applicant and incorporation into primary RCPs. Approximate Dollar Value: Proprietary. To support construction of four (4) Westinghouse AP–1000 pressurized water reactors (PWRs) authorized for export by NRC license XR169/01 to Sanmen and Haiyang nuclear power plants. Applicant seeks to add one new ultimate consignee (testing facility for complete AP–1000 RCP) and four (4) new intermediate consignees (processing facilities to finish RCP parts) to the consignees listed on XR169/01. For the U.S. Nuclear Regulatory Commission. Dated this 11th day of June 2008 at Rockville, Maryland. Margaret M. Doane, Director, Office of International Programs. [FR Doc. E8–14002 Filed 6–19–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–352 and 50–353] jlentini on PROD1PC65 with NOTICES Limerick Generating Station, Units 1 and 2; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License Nos. NPF– 39 and NPF–85 issued to Exelon Generation Company, LLC (the licensee) for operation of Limerick Generating Station (LGS), Unit Nos. 1 and 2, located in Montgomery County, Pennsylvania. The proposed amendment would increase the required minimum volume of fuel oil in the emergency diesel generator (EDG) day tanks from 200 gallons to 250 gallons, enough for 1 hour of continuous operation of the associated EDG at rated load. This change is necessitated by a revision to the LGS design analysis of EDG fuel consumption that accounts for VerDate Aug<31>2005 16:53 Jun 19, 2008 Jkt 214001 parameters not considered in the original analysis, including the use of ultra-low sulphur diesel fuel oil. Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission’s regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change involves increasing the minimum volume of fuel oil required to be maintained in each emergency diesel generator (EDG) fuel oil day tank. The proposed minimum volume of fuel oil ensures that sufficient fuel oil will be available to allow each EDG to operate for PO 00000 Frm 00053 Fmt 4703 Sfmt 4703 Country of destination People’s Republic of China. one hour at continuous rated load in accordance with the current licensing basis described in Limerick Generating Station (LGS) Updated Final Safety Analysis Report (UFSAR), Section 9.5.4. The proposed amendment has no effect on the performance or operation of the EDGs, and will not affect the long-term reliability of the EDGs. The EDGs will continue to operate as designed to supply the electrical loads assumed to mitigate the consequences of accidents previously evaluated. The proposed change to the EDG fuel oil day tank minimum volume requirement has no effect on accident initiators or assumptions of analyzed events. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. No permanent physical changes to the EDGs, the EDG fuel oil day tanks, or the fuel oil storage and transfer system are involved with the proposed change. The proposed change does not involve the permanent installation of any new or different type of equipment. Operation of the EDGs is associated with mitigating the consequences of an accident, and not accident prevention or initiation. The proposed change ensures that the EDGs will continue to perform their design function. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. There is no defined margin of safety that is affected by the minimum required volume of fuel oil maintained in the EDG fuel oil day E:\FR\FM\20JNN1.SGM 20JNN1

Agencies

[Federal Register Volume 73, Number 120 (Friday, June 20, 2008)]
[Notices]
[Pages 35167-35168]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-14002]


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NUCLEAR REGULATORY COMMISSION


Application for a License To Export Major Components for Nuclear 
Reactors

    Pursuant to 10 CFR 110.70 (b)(1) ``Public Notice of Receipt of an 
Application,'' please take notice that the Nuclear Regulatory 
Commission (NRC) has received the following request for an export 
license. Copies of the request are available electronically through 
ADAMS and can be accessed through the Public Electronic Reading Room 
(PERR) link http://www.nrc.gov/reading-rm.html at the NRC Homepage.
    A request for a hearing or petition for leave to intervene may be 
filed within thirty days after publication of this notice in the 
Federal Register. Any request for hearing or petition for leave to 
intervene shall be served by the requestor or petitioner upon the 
applicant, the Office of the General Counsel, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555; the Secretary, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555; and the Executive 
Secretary, U.S. Department of State, Washington, DC 20520.
    A request for a hearing or petition for leave to intervene may be 
filed with the NRC electronically in accordance with NRC's E-Filing 
rule promulgated in August 2007, 72 FR 49139 (Aug. 28, 2007). 
Information about filing electronically is available on the NRC's 
public Web site at http://www.nrc.gov/site-help/e-submittals.html. To 
ensure timely electronic filing, at least five days prior to the filing 
deadline, the petitioner/requestor should contact the Office of the 
Secretary by e-mail at HEARINGDOCKET@NRC.GOV, or by calling (301) 415-
1677, to request a digital ID certificate and allow for the creation of 
an electronic docket.
    In addition to a request for hearing or petition for leave to 
intervene, written comments, in accordance with 10 CFR 110.81 should be 
submitted within thirty days after publication of this

[[Page 35168]]

notice in the Federal Register to Office of the Secretary, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555, Attention: Rulemaking and 
Adjudications.
    In its review of applications for licenses and license amendments 
involving exports of major components of a utilization facility as 
defined in 10 CFR Part 110 and noticed herein, the Commission does not 
evaluate the health, safety or environmental effects in the recipient 
nation of the facility or facilities to be exported.
    The information concerning this license application follows:

            NRC Application for License To Export Major Components of a Nuclear Utilization Facility
----------------------------------------------------------------------------------------------------------------
      Name of applicant, date of           Total quantity/
     application, date received,         description of major           End use           Country of destination
     application No., docket No.              components
----------------------------------------------------------------------------------------------------------------
Curtiss-Wright Electro-Mechanical      As specified in 10 CFR   To support construction  People's Republic of
 Corporation, May 14, 2008, May 15,     Part 110, Appendix A     of four (4)              China.
 2008, XR172, 11005752.                 Items (4) and (9), one   Westinghouse AP-1000
                                        (1) complete primary     pressurized water
                                        reactor coolant pump     reactors (PWRs)
                                        (RCP) or major sub-      authorized for export
                                        assemblies thereof,      by NRC license XR169/
                                        and various raw          01 to Sanmen and
                                        materials and parts/     Haiyang nuclear power
                                        components to be         plants. Applicant
                                        processed into           seeks to add one new
                                        finished parts,          ultimate consignee
                                        components, sub-         (testing facility for
                                        assemblies and           complete AP-1000 RCP)
                                        assemblies in the        and four (4) new
                                        People's Republic of     intermediate
                                        China for return to      consignees (processing
                                        applicant and            facilities to finish
                                        incorporation into       RCP parts) to the
                                        primary RCPs.            consignees listed on
                                        Approximate Dollar       XR169/01.
                                        Value: Proprietary.
----------------------------------------------------------------------------------------------------------------

    For the U.S. Nuclear Regulatory Commission.

    Dated this 11th day of June 2008 at Rockville, Maryland.

Margaret M. Doane,
Director, Office of International Programs.
[FR Doc. E8-14002 Filed 6-19-08; 8:45 am]
BILLING CODE 7590-01-P