Exelon Generation Company, LLC; Byron Station, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact, 32144-32145 [E6-8580]

Download as PDF 32144 Federal Register / Vol. 71, No. 106 / Friday, June 2, 2006 / Notices telephone at 301–415–7233, or by Internet electronic mail to infocollects@nrc.gov. Dated at Rockville, Maryland, this 25th day of May 2006. For the Nuclear Regulatory Commission. Brenda Jo. Shelton, NRC Clearance Officer, Office of the Chief Information Officer. [FR Doc. E6–8583 Filed 6–1–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–346] jlentini on PROD1PC65 with NOTICES FirstEnergy Nuclear Operating Company and FirstEnergy Nuclear Generation Corp.; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of FirstEnergy Nuclear Operating Company and FirstEnergy Nuclear Generation Corp. (FENOC) to withdraw its May 22, 2005, application for proposed amendment to Facility Operating License No. NPF–3 for the Davis-Besse Nuclear Power Station (DBNPS), Unit 1, located in Ottawa County. The proposed amendment would have revised the technical specifications pertaining to a qualified alternate repair criteria for axial tube end cracking indications in the DBNPS once through steam generator tubes. Specifically, the proposed amendment would revise the TS surveillance requirements for the steam generator inservice inspection to include tube end cracking alternate repair criteria. The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on July 5, 2005 (70 FR 38720). However, by letter dated February 16, 2006, in response to Generic Letter 2006–01, ‘‘Steam Generator Tube Integrity and Associated Technical Specifications,’’ FENOC committed to submit a license amendment application by May 31, 2006, proposing to amend the DBNPS TS to be consistent with TS Task Force (TSTF)–449, ‘‘Steam Generator Tube Integrity,’’ Revision 4. Since this new license application will be incompatible with the changes proposed in the earlier license amendment application, by letter dated April 20, 2006, FENOC withdrew the May 22, 2005, amendment request. FENOC plans to resubmit the license amendment application at a later date. VerDate Aug<31>2005 18:05 Jun 01, 2006 Jkt 208001 For further details with respect to this action, see the application for amendment dated May 22, 2005, and the licensees’ letter dated April 20, 2006, 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 Systems (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, https:// www.nrc.gov/reading-rm.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 e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 25th day of May 2006. For the Nuclear Regulatory Commission. Stephen J. Campbell, Project Manager, Plant Licensing Branch III– 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E6–8581 Filed 6–1–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. STN 50–454 and STN 50–455] Exelon Generation Company, LLC; Byron Station, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) section 50.44, 10 CFR 50.46, and 10 CFR part 50, Appendix K, for Facility Operating Licenses Nos. NPF–37 and NPF–66, issued to Exelon Generation Company, LLC (Exelon, the licensee), for operation of Byron Station, Units 1 and 2, located in Ogle County, Illinois. Therefore, as required by 10 CFR 51.21, the NRC is issuing this environmental assessment and finding of no significant impact. Environmental Assessment Identification of the Proposed Action The proposed action would allow the licensee to place four lead test assemblies containing a limited number of AXIOMTM fuel rods into the Byron Station, Unit 1, core during the fall 2006 PO 00000 Frm 00117 Fmt 4703 Sfmt 4703 refueling outage. The four lead test assemblies will be placed in nonlimiting core locations. For subsequent cycles, two of the lead test assemblies will be placed into Byron Station, Unit 2, and two lead test assemblies will remain in Byron Station, Unit 1. The proposed action is in accordance with the licensee’s application dated September 23, 2005. The Need for the Proposed Action Pursuant to 10 CFR 50.12, ‘‘Specific exemptions,’’ Exelon has requested exemptions from 10 CFR 50.44, ‘‘Combustible gas control for nuclear power reactors,’’ 10 CFR 50.46, ‘‘Acceptance criteria for emergency core cooling systems [EECS] for light-water nuclear power reactors,’’ and Appendix K to 10 CFR part 50, ‘‘ECCS Evaluation Models.’’ The regulation at 10 CFR 50.44 specifies requirements for the control of hydrogen gas generated after a postulated loss-of-coolant accident (LOCA) for reactors fueled with zirconium-clad fuel. Section 50.46 contains acceptance criteria for ECCS for reactors fueled with zircaloy or ZIRLOTM clad fuel. In addition, Appendix K to 10 CFR part 50 requires that the Baker-Just equation be used to predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal-water reaction. The exemption request relates solely to the specific types of cladding material specified in these regulations. As written, the regulations presume the use of zircaloy or ZIRLOTM fuel rod cladding. Thus, an exemption from the requirements of 10 CFR 50.44, 10 CFR 50.46, and Appendix K to 10 CFR part 50 is needed to irradiate lead test assemblies employing AXIOMTM developmental clad alloys at Byron Station, Units 1 and 2. The proposed action will use the irradiation of the lead test assemblies incorporating the developmental cladding to provide data on fuel and material performances to support future licensing activities. Environmental Impacts of the Proposed Action The NRC has completed its safety evaluation of the proposed action and concludes that specific application of the limitations on fuel cladding material in 10 CFR 50.44, 10 CFR 50.46, and 10 CFR part 50 Appendix K to the lead test assemblies is not necessary for the licensee to achieve their underlying purposes. In addition, the NRC staff has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to public health and safety, and is E:\FR\FM\02JNN1.SGM 02JNN1 Federal Register / Vol. 71, No. 106 / Friday, June 2, 2006 / Notices consistent with the common defense and security. The details of the NRC staff’s safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation. The proposed action will not significantly increase the probability or consequences of accidents. No changes are being made in the types of effluents that may be released off site. There is no significant increase in the amount of any effluent released off site. There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological environmental impacts associated with the proposed action. With regard to potential nonradiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological environmental impacts associated with the proposed action. Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action. Environmental Impacts of the Alternatives to the Proposed Action As an alternative to the proposed action, the NRC staff considered denial of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar. Alternative Use of Resources The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for Byron Station, Units 1 and 2, NUREG–0848, dated April 1982. jlentini on PROD1PC65 with NOTICES Agencies and Persons Consulted In accordance with its stated policy, on April 7, 2006, the NRC staff consulted with the Illinois State official, Mr. Frank Niziolek of the Illinois Emergency Management Agency, regarding the environmental impact of the proposed action. The State official had no comments. Finding of No Significant Impact On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the VerDate Aug<31>2005 18:05 Jun 01, 2006 Jkt 208001 NRC has determined not to prepare an environmental impact statement for the proposed action. For further details with respect to the proposed action, see the licensee’s letter dated September 23, 2005. 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, 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 PDR Reference staff by telephone at 1–800– 397–4209 or 301–415–4737, or send an e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 25th day of May 2006. For the Nuclear Regulatory Commission. Robert F. Kuntz, Project Manager, Plant Licensing Branch III– 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E6–8580 Filed 6–1–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Sunshine Act Meeting 32145 U.S.C. 552b(e) and § 9.107(a) of the Commission’s rules that Affirmation of ‘‘Louisiana Energy Services, L.P. (National Enrichment Facility) Intervenors’ Petition for Review LBP– 06–08 and LBP–06–09’’ be held June 2, 2006, and on less than one week’s notice to the public. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: https://www.nrc.gov/what-we-do/ policy-making/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 the NRC’s Disability Program Coordinator, Deborah Chan, at 301–415–7041, TDD: 301–415–2100, or by e-mail at DLC@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. * * * * * This notice is distributed by mail to several hundred 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). In addition, distribution of this meeting notice over the Internet system is available. If you are interested in receiving this Commission meeting schedule electronically, please send an electronic message to dwk@nrc.gov. Week of May 29, 2006. Commissioner’s Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. ADDITIONAL MATTERS TO BE CONSIDERED: Dated: May 30, 2006. R. Michelle Schroll, Office of the Secretary. [FR Doc. 06–5083 Filed 5–31–06; 10:25 am] Week of May 29, 2006 BILLING CODE 7590–01–M DATE: PLACE: Friday, June 2, 2006 3:30 p.m.—Affirmation Session (Public Meeting) (Tentative) a. Louisiana Energy Services, L.P. (National Enrichment Facility) Intervenors’ Petition for Review of LBP–06–08 and LPT–06–09. (Tentative) * * * * * 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: Michelle Schroll, (301) 415–1662. * * * * * Additional Information By a vote of 5–0 on May 30, 2006, the Commission determined pursuant to PO 00000 Frm 00118 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement to Modify Requirements Regarding the Addition of LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process AGENCY: Nuclear Regulatory Commission. ACTION: Request for comment. SUMMARY: Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and model E:\FR\FM\02JNN1.SGM 02JNN1

Agencies

[Federal Register Volume 71, Number 106 (Friday, June 2, 2006)]
[Notices]
[Pages 32144-32145]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-8580]


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

 NUCLEAR REGULATORY COMMISSION

[Docket Nos. STN 50-454 and STN 50-455]


Exelon Generation Company, LLC; Byron Station, Unit Nos. 1 and 2; 
Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an exemption from Title 10 of the Code of Federal 
Regulations (10 CFR) section 50.44, 10 CFR 50.46, and 10 CFR part 50, 
Appendix K, for Facility Operating Licenses Nos. NPF-37 and NPF-66, 
issued to Exelon Generation Company, LLC (Exelon, the licensee), for 
operation of Byron Station, Units 1 and 2, located in Ogle County, 
Illinois. Therefore, as required by 10 CFR 51.21, the NRC is issuing 
this environmental assessment and finding of no significant impact.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would allow the licensee to place four lead 
test assemblies containing a limited number of AXIOMTM fuel 
rods into the Byron Station, Unit 1, core during the fall 2006 
refueling outage. The four lead test assemblies will be placed in non-
limiting core locations. For subsequent cycles, two of the lead test 
assemblies will be placed into Byron Station, Unit 2, and two lead test 
assemblies will remain in Byron Station, Unit 1.
    The proposed action is in accordance with the licensee's 
application dated September 23, 2005.

The Need for the Proposed Action

    Pursuant to 10 CFR 50.12, ``Specific exemptions,'' Exelon has 
requested exemptions from 10 CFR 50.44, ``Combustible gas control for 
nuclear power reactors,'' 10 CFR 50.46, ``Acceptance criteria for 
emergency core cooling systems [EECS] for light-water nuclear power 
reactors,'' and Appendix K to 10 CFR part 50, ``ECCS Evaluation 
Models.'' The regulation at 10 CFR 50.44 specifies requirements for the 
control of hydrogen gas generated after a postulated loss-of-coolant 
accident (LOCA) for reactors fueled with zirconium-clad fuel. Section 
50.46 contains acceptance criteria for ECCS for reactors fueled with 
zircaloy or ZIRLOTM clad fuel. In addition, Appendix K to 10 
CFR part 50 requires that the Baker-Just equation be used to predict 
the rates of energy release, hydrogen concentration, and cladding 
oxidation from the metal-water reaction.
    The exemption request relates solely to the specific types of 
cladding material specified in these regulations. As written, the 
regulations presume the use of zircaloy or ZIRLOTM fuel rod 
cladding. Thus, an exemption from the requirements of 10 CFR 50.44, 10 
CFR 50.46, and Appendix K to 10 CFR part 50 is needed to irradiate lead 
test assemblies employing AXIOMTM developmental clad alloys 
at Byron Station, Units 1 and 2.
    The proposed action will use the irradiation of the lead test 
assemblies incorporating the developmental cladding to provide data on 
fuel and material performances to support future licensing activities.

Environmental Impacts of the Proposed Action

    The NRC has completed its safety evaluation of the proposed action 
and concludes that specific application of the limitations on fuel 
cladding material in 10 CFR 50.44, 10 CFR 50.46, and 10 CFR part 50 
Appendix K to the lead test assemblies is not necessary for the 
licensee to achieve their underlying purposes. In addition, the NRC 
staff has determined that, pursuant to 10 CFR 50.12(a), the exemption 
is authorized by law, will not present an undue risk to public health 
and safety, and is

[[Page 32145]]

consistent with the common defense and security.
    The details of the NRC staff's safety evaluation will be provided 
in the exemption that will be issued as part of the letter to the 
licensee approving the exemption to the regulation.
    The proposed action will not significantly increase the probability 
or consequences of accidents. No changes are being made in the types of 
effluents that may be released off site. There is no significant 
increase in the amount of any effluent released off site. There is no 
significant increase in occupational or public radiation exposure. 
Therefore, there are no significant radiological environmental impacts 
associated with the proposed action.
    With regard to potential non-radiological impacts, the proposed 
action does not have a potential to affect any historic sites. It does 
not affect non-radiological plant effluents and has no other 
environmental impact. Therefore, there are no significant non-
radiological environmental impacts associated with the proposed action.
    Accordingly, the NRC concludes that there are no significant 
environmental impacts associated with the proposed action.

Environmental Impacts of the Alternatives to the Proposed Action

    As an alternative to the proposed action, the NRC staff considered 
denial of the proposed action (i.e., the ``no-action'' alternative). 
Denial of the application would result in no change in current 
environmental impacts. The environmental impacts of the proposed action 
and the alternative action are similar.

Alternative Use of Resources

    The action does not involve the use of any different resources than 
those previously considered in the Final Environmental Statement for 
Byron Station, Units 1 and 2, NUREG-0848, dated April 1982.

Agencies and Persons Consulted

    In accordance with its stated policy, on April 7, 2006, the NRC 
staff consulted with the Illinois State official, Mr. Frank Niziolek of 
the Illinois Emergency Management Agency, regarding the environmental 
impact of the proposed action. The State official had no comments.

Finding of No Significant Impact

    On the basis of the environmental assessment, the NRC concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the NRC has determined 
not to prepare an environmental impact statement for the proposed 
action.
    For further details with respect to the proposed action, see the 
licensee's letter dated September 23, 2005. 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, 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 PDR Reference staff by telephone at 1-800-397-4209 or 301-415-4737, 
or send an e-mail to pdr@nrc.gov.

    Dated at Rockville, Maryland, this 25th day of May 2006.

    For the Nuclear Regulatory Commission.
Robert F. Kuntz,
Project Manager, Plant Licensing Branch III-2, Division of Operating 
Reactor Licensing, Office of Nuclear Reactor Regulation.
 [FR Doc. E6-8580 Filed 6-1-06; 8:45 am]
BILLING CODE 7590-01-P
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