Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Exemption, 9620-9622 [2010-4380]

Download as PDF 9620 Federal Register / Vol. 75, No. 41 / Wednesday, March 3, 2010 / Notices Assessment (EA) in support of this exemption. Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate. Environmental Assessment Identification of the Proposed Action The proposed action would allow SCE&G to use Optimized ZIRLOTM, an advanced alloy fuel cladding material for pressurized-water reactors. The proposed action is in accordance with the licensee’s application dated June 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091620072). The Need for the Proposed Action The proposed action is needed so that SCE&G can use Optimized ZIRLOTM, an advanced alloy for fuel rod cladding and other assembly structural components at the VCSNS. Section 50.46 of 10 CFR and 10 CFR part 50, appendix K, make no provisions for use of fuel rods clad in a material other than zircaloy or ZIRLOTM. Since the chemical composition of the Optimized ZIRLOTM alloy differs from the specifications for zircaloy or ZIRLO, a plant-specific exemption is required to allow the use of the Optimized ZIRLOTM alloy as a cladding material or in other assembly structural components at the VCSNS. mstockstill on DSKH9S0YB1PROD with NOTICES Environmental Impacts of the Proposed Action The NRC has completed its environmental assessment of the proposed exemption. The staff has concluded that the proposed action to approve the use of an additional fuel rod cladding material would not significantly affect plant safety and would not have a significant adverse effect on the probability of an accident occurring. The proposed action would not result in an increased radiological hazard beyond those previously analyzed in the Final Environmental Statement for the Virgil C. Summer Nuclear Station, Unit No. 1, NUREG–0719, dated May 1981 (ADAMS Accession No. ML072750234) and the Generic Environmental Impact Statement for License Renewal of Nuclear Plants, NUREG–1437, Supplement 15, dated February 2004 (ADAMS Accession No. ML040540718). 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. VerDate Nov<24>2008 16:08 Mar 02, 2010 Jkt 220001 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 MagnusonSteven’s 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 impacts are expected as a result of the proposed exemption. Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action. 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, if granted. Environmental Impacts of the Alternatives to the Proposed Action As an alternative to the proposed action, the staff considered denial of the proposed action (i.e., the ‘‘no-action’’ alternative). Denial of the application request 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 considered in the Final Environmental Statement for the Virgil C. Summer Nuclear Station, Unit No. 1, NUREG– 0719, dated May 1981 (ADAMS Accession No. ML072750234) and the Generic Environmental Impact Statement for License Renewal of Nuclear Plants, NUREG–1437, Supplement 15, dated February 2004 (ADAMS Accession No. ML040540718). Agencies and Persons Consulted In accordance with its stated policy, on January 11, 2010, the staff consulted with the South Carolina State official, Susan Jenkins of the South Carolina Department of Health and Environmental Control, regarding the environmental impact of the proposed action. The State official had no comments. PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 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. Further Information Documents related to this action, including the application for an exemption and license amendment and supporting documentation, are available electronically at the NRC’s Electronic Reading Room at https://www.nrc.gov/ reading-rm/adams.html. From this site, you can access the NRC’s Agencywide Document Access and Management System (ADAMS), which provides text and image files of NRC’s public documents. The ADAMS accession number for the document related to this notice, ‘‘License Amendment Request for Use of Optimized ZirloTM Fuel Rod Cladding,’’ dated June 9, 2009, is ML091620072. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the NRC Public Document Room (PDR) Reference staff at 1–800–397–4209, 301–415–4737 or by e-mail to pdr.resource@nrc.gov. The document may also be viewed electronically on the public computers located at the NRC’s Public Document Room (PDR), O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Dated at Rockville, Maryland, this 24th day of February 2010. For the Nuclear Regulatory Commission. Robert E. Martin, Senior Project Manager, Plant Licensing Branch II–1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–4383 Filed 3–2–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–321 and 50–366; NRC– 2010–0024] Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Exemption 1.0 Background Southern Nuclear Operating Company, Inc. (SNC, the licensee), is the holder of Renewed Facility Operating License Nos. DPR–57 and E:\FR\FM\03MRN1.SGM 03MRN1 Federal Register / Vol. 75, No. 41 / Wednesday, March 3, 2010 / Notices mstockstill on DSKH9S0YB1PROD with NOTICES NPF–5, which authorizes operation of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (HNP). The licenses provide, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now, or hereafter, in effect. The facility consists of two boilingwater reactors located in Appling County, Georgia. 2.0 Request/Action Title 10 of the Code of Federal Regulations (10 CFR), Part 73, ‘‘Physical protection of plants and materials,’’ Section 73.55, ‘‘Requirements for physical protection of licensed activities in nuclear power reactors against radiological sabotage,’’ published March 27, 2009, effective May 26, 2009, with a full implementation date of March 31, 2010, requires licensees to protect, with high assurance, against radiological sabotage by designing and implementing comprehensive site security programs. The amendments to 10 CFR 73.55 published on March 27, 2009, establish and update generically applicable security requirements similar to those previously imposed by Commission orders issued after the terrorist attacks of September 11, 2001, and implemented by licensees. In addition, the amendments to 10 CFR 73.55 include additional requirements to further enhance site security based upon insights gained from implementation of the post September 11, 2001, security orders. It is from one requirement of these new requirements that HNP now seeks an exemption from the March 31, 2010, implementation date. All other physical security requirements established by this recent rulemaking have already been or will be implemented by the licensee by March 31, 2010. By letter dated November 6, 2009, as supplemented by letter dated November 20, 2009, the licensee requested an exemption in accordance with 10 CFR 73.5, ‘‘Specific exemptions.’’ The licensee’s letters contain proprietary information and, accordingly, those portions are not available to the public. The licensee has requested an exemption from the March 31, 2010, compliance date stating that a number of issues will present a significant challenge to timely completion of the project related to a specific requirement in 10 CFR Part 73. Specifically, the request is to extend the compliance date for one specific requirement from the current March 31, 2010, deadline to December 6, 2010. Being granted this exemption for the one item will allow the licensee to complete the VerDate Nov<24>2008 16:08 Mar 02, 2010 Jkt 220001 modifications designed to update equipment and incorporate state-of-theart technology to meet the noted regulatory requirement. 3.0 Discussion of Part 73 Schedule Exemptions From the March 31, 2010, Full Implementation Date Pursuant to 10 CFR 73.55(a)(1), ‘‘By March 31, 2010, each nuclear power reactor licensee, licensed under 10 CFR Part 50, shall implement the requirements of this section through its Commission-approved Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan referred to collectively hereafter as ‘security plans.’ ’’ Pursuant to 10 CFR 73.5, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 73 when the exemptions are authorized by law, and will not endanger life or property or the common defense and security, and are otherwise in the public interest. NRC approval of this exemption would; as noted above, allow an extension from March 31, 2010, to December 6, 2010, for the implementation date for one specific requirement of the new rule. The NRC staff has determined that granting of the licensee’s proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission’s regulations. Therefore, the exemption is authorized by law. In the draft final rule provided to the Commission (SECY–08–0099 dated July 9, 2008), the NRC staff proposed that the requirements of the new regulation be met within 180 days. The Commission directed a change from 180 days to approximately 1 year for licensees to fully implement the new requirements. This change was incorporated into the final rule. From this, it is clear that the Commission wanted to provide a reasonable timeframe for licensees to achieve full compliance. As noted in the final rule, the Commission also anticipated that licensees would have to conduct site specific analyses to determine what changes were necessary to implement the rule’s requirements, and that changes could be accomplished through a variety of licensing mechanisms, including exemptions. Since issuance of the final rule, the Commission has rejected a generic industry request to extend the rule’s compliance date for all operating nuclear power plants, but noted that the Commission’s regulations provide mechanisms for individual licensees, with good cause, to apply for relief from the compliance date PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 9621 (Reference: June 4, 2009, letter from R.W. Borchardt, NRC, to M.S. Fertel, Nuclear Energy Institute). The licensee’s request for an exemption is therefore consistent with the approach set forth by the Commission as discussed in the June 4, 2009, letter. HNP Schedule Exemption Request The licensee provided detailed information in its letter dated November 6, 2009, as supplemented November 20, 2009, requesting an exemption. It describes a comprehensive plan to install equipment related to a certain requirement in the new Part 73 rule and provides a timeline for achieving full compliance with the new regulation. The submittals contain proprietary information regarding the site security plan, details of the specific requirement of the regulation for which the site cannot be in compliance by the March 31, 2010, deadline and why, the required changes to the site’s security configuration, and a timeline with critical path activities that will bring the licensee into full compliance by December 6, 2010. The timeline provides dates indicating (1) when various phases of the project begin and end (i.e., design, field construction), (2) outages scheduled for each unit, and (3) when critical equipment will be ordered, installed, tested and become operational. Notwithstanding the schedular exemption for this limited requirement, the licensee will continue to be in compliance with all other applicable physical security requirements as described in 10 CFR 73.55 and reflected in its current NRC approved physical security program. By December 6, 2010, HNP will be in full compliance with all the regulatory requirements of 10 CFR 73.55, as issued on March 27, 2009. 4.0 Conclusion for Part 73 Schedule Exemption Request The NRC staff has reviewed the licensee’s submittals and concludes that the licensee has provided adequate justification for its request for an extension of the compliance date to December 6, 2010, with regard to a specific requirement of 10 CFR 73.55. Accordingly, the Commission has determined that pursuant to 10 CFR 73.5, ‘‘Specific exemptions,’’ an exemption from the March 31, 2010, compliance date is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants the requested exemption. The NRC staff has determined that the long-term benefits that will be realized E:\FR\FM\03MRN1.SGM 03MRN1 9622 Federal Register / Vol. 75, No. 41 / Wednesday, March 3, 2010 / Notices when the HNP equipment installation is complete justifies extending the full compliance date with regard to the specific requirement of 10 CFR 73.55. The security measure, that HNP needs additional time to implement, is a new requirement imposed by the March 27, 2009, amendments to 10 CFR 73.55, and is in addition to those required by the security orders issued in response to the events of September 11, 2001. Therefore, it is concluded that the licensee’s actions are in the best interest of protecting the public health and safety through the security changes that will result from granting this exemption. As per the licensee’s request and the NRC’s regulatory authority to grant an exemption from the March 31, 2010, implementation deadline for the requirement specified in the SNC letter dated November 6, 2009, as supplemented November 20, 2009, the licensee is required to be in full compliance by December 6, 2010. In achieving compliance, the licensee is reminded that it is responsible for determining the appropriate licensing mechanism (i.e., 10 CFR 50.54(p) or 10 CFR 50.90) for incorporation of all necessary changes to its security plans. Pursuant to 10 CFR 51.32, ‘‘Finding of no significant impact,’’ the Commission has previously determined that the granting of this exemption will not have a significant effect on the quality of the human environment (75 FR 3761; dated January 22, 2010). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 24th day of February 2010. For the Nuclear Regulatory Commission. Allen G. Howe, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–4380 Filed 3–2–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–424 and 50–425; NRC– 2010–0023] mstockstill on DSKH9S0YB1PROD with NOTICES Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 1 and 2; Exemption 1.0 Background Southern Nuclear Operating Company, Inc. (SNC, the licensee), is the holder of Renewed Facility Operating License Nos. NPF–68 and NPF–81, which authorizes operation of the Vogtle Electric Generating Plant, Units 1 and 2 (VEGP). The licenses VerDate Nov<24>2008 16:08 Mar 02, 2010 Jkt 220001 provide, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facility consists of two pressurized-water reactors located in Burke County, Georgia. 2.0 Request/Action Title 10 of the Code of Federal Regulations (10 CFR), Part 73, ‘‘Physical protection of plants and materials,’’ Section 73.55, ‘‘Requirements for physical protection of licensed activities in nuclear power reactors against radiological sabotage,’’ published March 27, 2009, effective May 26, 2009, with a full implementation date of March 31, 2010, requires licensees to protect, with high assurance, against radiological sabotage by designing and implementing comprehensive site security programs. The amendments to 10 CFR 73.55 published on March 27, 2009 establish and update generically applicable security requirements similar to those previously imposed by Commission orders issued after the terrorist attacks of September 11, 2001, and implemented by licensees. In addition, the amendments to 10 CFR 73.55 include additional requirements to further enhance site security based upon insights gained from implementation of the post September 11, 2001, security orders. It is from one requirement of these new requirements that VEGP now seeks an exemption from the March 31, 2010, implementation date. All other physical security requirements established by this recent rulemaking have already been or will be implemented by the licensee by March 31, 2010. By letter dated November 6, 2009, as supplemented by letter dated November 20, 2009, the licensee requested an exemption in accordance with 10 CFR 73.5, ‘‘Specific exemptions.’’ The licensee’s letters contain proprietary information and, accordingly, those portions are not available to the public. The licensee has requested an exemption from the March 31, 2010, compliance date stating that a number of issues will present a significant challenge to timely completion of the project related to a specific requirement in 10 CFR Part 73. Specifically, the request is to extend the compliance date for one specific requirement from the current March 31, 2010, deadline to September 27, 2010. Being granted this exemption for the one item will allow the licensee to complete the modifications designed to update equipment and incorporate state-of-the- PO 00000 Frm 00051 Fmt 4703 Sfmt 4703 art technology to meet the noted regulatory requirement. 3.0 Discussion of Part 73 Schedule Exemptions From the March 31, 2010, Full Implementation Date Pursuant to 10 CFR 73.55(a)(1), ‘‘By March 31, 2010, each nuclear power reactor licensee, licensed under 10 CFR Part 50, shall implement the requirements of this section through its Commission-approved Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan referred to collectively hereafter as ‘security plans.’ ’’ Pursuant to 10 CFR 73.5, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 73 when the exemptions are authorized by law, and will not endanger life or property or the common defense and security, and are otherwise in the public interest. NRC approval of this exemption would; as noted above, allow an extension from March 31, 2010, to September 27, 2010, for the implementation date for one specific requirement of the new rule. The NRC staff has determined that granting of the licensee’s proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission’s regulations. Therefore, the exemption is authorized by law. In the draft final rule provided to the Commission (SECY–08–0099 dated July 9, 2008), the NRC staff proposed that the requirements of the new regulation be met within 180 days. The Commission directed a change from 180 days to approximately 1 year for licensees to fully implement the new requirements. This change was incorporated into the final rule. From this, it is clear that the Commission wanted to provide a reasonable timeframe for licensees to achieve full compliance. As noted in the final rule, the Commission also anticipated that licensees would have to conduct site specific analyses to determine what changes were necessary to implement the rule’s requirements, and that changes could be accomplished through a variety of licensing mechanisms, including exemptions. Since issuance of the final rule, the Commission has rejected a generic industry request to extend the rule’s compliance date for all operating nuclear power plants, but noted that the Commission’s regulations provide mechanisms for individual licensees, with good cause, to apply for relief from the compliance date (Reference: June 4, 2009, letter from R.W. Borchardt, NRC, to M.S. Fertel, E:\FR\FM\03MRN1.SGM 03MRN1

Agencies

[Federal Register Volume 75, Number 41 (Wednesday, March 3, 2010)]
[Notices]
[Pages 9620-9622]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-4380]


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

NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-321 and 50-366; NRC-2010-0024]


Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear 
Plant, Units 1 and 2; Exemption

1.0 Background

    Southern Nuclear Operating Company, Inc. (SNC, the licensee), is 
the holder of Renewed Facility Operating License Nos. DPR-57 and

[[Page 9621]]

NPF-5, which authorizes operation of the Edwin I. Hatch Nuclear Plant, 
Units 1 and 2 (HNP). The licenses provide, among other things, that the 
facility is subject to all rules, regulations, and orders of the U.S. 
Nuclear Regulatory Commission (NRC, the Commission) now, or hereafter, 
in effect.
    The facility consists of two boiling-water reactors located in 
Appling County, Georgia.

2.0 Request/Action

    Title 10 of the Code of Federal Regulations (10 CFR), Part 73, 
``Physical protection of plants and materials,'' Section 73.55, 
``Requirements for physical protection of licensed activities in 
nuclear power reactors against radiological sabotage,'' published March 
27, 2009, effective May 26, 2009, with a full implementation date of 
March 31, 2010, requires licensees to protect, with high assurance, 
against radiological sabotage by designing and implementing 
comprehensive site security programs. The amendments to 10 CFR 73.55 
published on March 27, 2009, establish and update generically 
applicable security requirements similar to those previously imposed by 
Commission orders issued after the terrorist attacks of September 11, 
2001, and implemented by licensees. In addition, the amendments to 10 
CFR 73.55 include additional requirements to further enhance site 
security based upon insights gained from implementation of the post 
September 11, 2001, security orders. It is from one requirement of 
these new requirements that HNP now seeks an exemption from the March 
31, 2010, implementation date. All other physical security requirements 
established by this recent rulemaking have already been or will be 
implemented by the licensee by March 31, 2010.
    By letter dated November 6, 2009, as supplemented by letter dated 
November 20, 2009, the licensee requested an exemption in accordance 
with 10 CFR 73.5, ``Specific exemptions.'' The licensee's letters 
contain proprietary information and, accordingly, those portions are 
not available to the public. The licensee has requested an exemption 
from the March 31, 2010, compliance date stating that a number of 
issues will present a significant challenge to timely completion of the 
project related to a specific requirement in 10 CFR Part 73. 
Specifically, the request is to extend the compliance date for one 
specific requirement from the current March 31, 2010, deadline to 
December 6, 2010. Being granted this exemption for the one item will 
allow the licensee to complete the modifications designed to update 
equipment and incorporate state-of-the-art technology to meet the noted 
regulatory requirement.

3.0 Discussion of Part 73 Schedule Exemptions From the March 31, 2010, 
Full Implementation Date

    Pursuant to 10 CFR 73.55(a)(1), ``By March 31, 2010, each nuclear 
power reactor licensee, licensed under 10 CFR Part 50, shall implement 
the requirements of this section through its Commission-approved 
Physical Security Plan, Training and Qualification Plan, Safeguards 
Contingency Plan, and Cyber Security Plan referred to collectively 
hereafter as `security plans.' '' Pursuant to 10 CFR 73.5, the 
Commission may, upon application by any interested person or upon its 
own initiative, grant exemptions from the requirements of 10 CFR Part 
73 when the exemptions are authorized by law, and will not endanger 
life or property or the common defense and security, and are otherwise 
in the public interest.
    NRC approval of this exemption would; as noted above, allow an 
extension from March 31, 2010, to December 6, 2010, for the 
implementation date for one specific requirement of the new rule. The 
NRC staff has determined that granting of the licensee's proposed 
exemption will not result in a violation of the Atomic Energy Act of 
1954, as amended, or the Commission's regulations. Therefore, the 
exemption is authorized by law.
    In the draft final rule provided to the Commission (SECY-08-0099 
dated July 9, 2008), the NRC staff proposed that the requirements of 
the new regulation be met within 180 days. The Commission directed a 
change from 180 days to approximately 1 year for licensees to fully 
implement the new requirements. This change was incorporated into the 
final rule. From this, it is clear that the Commission wanted to 
provide a reasonable timeframe for licensees to achieve full 
compliance.
    As noted in the final rule, the Commission also anticipated that 
licensees would have to conduct site specific analyses to determine 
what changes were necessary to implement the rule's requirements, and 
that changes could be accomplished through a variety of licensing 
mechanisms, including exemptions. Since issuance of the final rule, the 
Commission has rejected a generic industry request to extend the rule's 
compliance date for all operating nuclear power plants, but noted that 
the Commission's regulations provide mechanisms for individual 
licensees, with good cause, to apply for relief from the compliance 
date (Reference: June 4, 2009, letter from R.W. Borchardt, NRC, to M.S. 
Fertel, Nuclear Energy Institute). The licensee's request for an 
exemption is therefore consistent with the approach set forth by the 
Commission as discussed in the June 4, 2009, letter.

HNP Schedule Exemption Request

    The licensee provided detailed information in its letter dated 
November 6, 2009, as supplemented November 20, 2009, requesting an 
exemption. It describes a comprehensive plan to install equipment 
related to a certain requirement in the new Part 73 rule and provides a 
timeline for achieving full compliance with the new regulation. The 
submittals contain proprietary information regarding the site security 
plan, details of the specific requirement of the regulation for which 
the site cannot be in compliance by the March 31, 2010, deadline and 
why, the required changes to the site's security configuration, and a 
timeline with critical path activities that will bring the licensee 
into full compliance by December 6, 2010. The timeline provides dates 
indicating (1) when various phases of the project begin and end (i.e., 
design, field construction), (2) outages scheduled for each unit, and 
(3) when critical equipment will be ordered, installed, tested and 
become operational.
    Notwithstanding the schedular exemption for this limited 
requirement, the licensee will continue to be in compliance with all 
other applicable physical security requirements as described in 10 CFR 
73.55 and reflected in its current NRC approved physical security 
program. By December 6, 2010, HNP will be in full compliance with all 
the regulatory requirements of 10 CFR 73.55, as issued on March 27, 
2009.

4.0 Conclusion for Part 73 Schedule Exemption Request

    The NRC staff has reviewed the licensee's submittals and concludes 
that the licensee has provided adequate justification for its request 
for an extension of the compliance date to December 6, 2010, with 
regard to a specific requirement of 10 CFR 73.55.
    Accordingly, the Commission has determined that pursuant to 10 CFR 
73.5, ``Specific exemptions,'' an exemption from the March 31, 2010, 
compliance date is authorized by law and will not endanger life or 
property or the common defense and security, and is otherwise in the 
public interest. Therefore, the Commission hereby grants the requested 
exemption.
    The NRC staff has determined that the long-term benefits that will 
be realized

[[Page 9622]]

when the HNP equipment installation is complete justifies extending the 
full compliance date with regard to the specific requirement of 10 CFR 
73.55. The security measure, that HNP needs additional time to 
implement, is a new requirement imposed by the March 27, 2009, 
amendments to 10 CFR 73.55, and is in addition to those required by the 
security orders issued in response to the events of September 11, 2001. 
Therefore, it is concluded that the licensee's actions are in the best 
interest of protecting the public health and safety through the 
security changes that will result from granting this exemption.
    As per the licensee's request and the NRC's regulatory authority to 
grant an exemption from the March 31, 2010, implementation deadline for 
the requirement specified in the SNC letter dated November 6, 2009, as 
supplemented November 20, 2009, the licensee is required to be in full 
compliance by December 6, 2010. In achieving compliance, the licensee 
is reminded that it is responsible for determining the appropriate 
licensing mechanism (i.e., 10 CFR 50.54(p) or 10 CFR 50.90) for 
incorporation of all necessary changes to its security plans.
    Pursuant to 10 CFR 51.32, ``Finding of no significant impact,'' the 
Commission has previously determined that the granting of this 
exemption will not have a significant effect on the quality of the 
human environment (75 FR 3761; dated January 22, 2010).
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 24th day of February 2010.

    For the Nuclear Regulatory Commission.
Allen G. Howe,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2010-4380 Filed 3-2-10; 8:45 am]
BILLING CODE 7590-01-P
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