FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption, 16524-16525 [2010-7375]

Download as PDF 16524 Federal Register / Vol. 75, No. 62 / Thursday, April 1, 2010 / Notices mstockstill on DSKH9S0YB1PROD with NOTICES licensee has provided adequate justification for its request for an extension of the compliance date with regard to the one specified requirement of 10 CFR 73.55 to February 3, 2011. Accordingly, the Commission has determined that pursuant to10 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. The NRC staff has determined that the long-term benefits that will be realized when the DBNPS equipment installation is complete, justifies extending the full compliance date with regard to the specified requirement of 10 CFR 73.55. The security measures DBNPS needs additional time to implement are new requirements imposed by March 27, 2009, amendments to 10 CFR 73.55, and are in addition to those required by the security orders issued in response to the events of September 11, 2001. Therefore, the NRC 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, deadline for the one item specified in the enclosure of FENOC letter dated November 30, 2009, the licensee is required to be in full compliance by February 3, 2011. 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 14635). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 26th day of March 2010. For the Nuclear Regulatory Commission. Joseph G. Giitter, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–7378 Filed 3–31–10; 8:45 am] BILLING CODE 7590–01–P VerDate Nov<24>2008 16:51 Mar 31, 2010 Jkt 220001 NUCLEAR REGULATORY COMMISSION [Docket No. 50–440; NRC–2010–0124] FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating License No. NFP–58, which authorizes operation of the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, 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 one boilingwater reactor located in Lake County, Ohio. 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 includes 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 of these new requirements that PNPP 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 30, 2009, as supplemented by letter dated December 23, 2009, the licensee requested an exemption in accordance with 10 CFR 73.5, ‘‘Specific exemptions.’’ The licensee’s November 30, 2009, letter contains proprietary and safeguards information and, accordingly, is not PO 00000 Frm 00103 Fmt 4703 Sfmt 4703 available to the public. The licensee has requested an exemption from the March 31, 2010, compliance date stating that it must complete a significant modification to the current site security configuration before all requirements can be met. Specifically, the request is for one specific requirement from the current March 31, 2010, deadline, to November 25, 2010. Being granted this exemption for the one item would allow the licensee to complete the modification and incorporate state-ofthe-art technology to meet or exceed regulatory requirements. 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. The approval of this exemption, as noted above, would allow an extension from March 31, 2010, until November 25, 2010, for one specified area of the new rule. As stated above, 10 CFR 73.5 allows the NRC to grant exemptions from the requirements of 10 CFR part 73. The NRC staff has determined that granting of the licensee’s proposed exemption would 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 Power Reactor Security provided to the Commission, 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 sitespecific analyses to determine what E:\FR\FM\01APN1.SGM 01APN1 Federal Register / Vol. 75, No. 62 / Thursday, April 1, 2010 / Notices 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 and discussed in the June 4, 2009, letter. mstockstill on DSKH9S0YB1PROD with NOTICES Perry Nuclear Power Plant Schedule Exemption Request The licensee provided detailed information in the enclosure of its November 30, 2009, letter, requesting an exemption. Enclosure 1 contains proprietary information regarding the site security plan, details of specific portions 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 would enable the licensee to achieve full compliance by November 25, 2010. The timeline provides dates indicating when (1) Construction will begin on various phases of the project, (2) outages are scheduled for the unit, and (3) critical equipment will be ordered, installed, tested and become operational. Notwithstanding the schedule exemption for this specific 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 November 25, 2010, PNPP 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 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 with regard to the one specified requirement of 10 CFR 73.55 to November 25, 2010. Accordingly, the Commission has determined that pursuant to 10 CFR 73.5, ‘‘Specific exemptions,’’ an exemption from the March 31, 2010, VerDate Nov<24>2008 16:51 Mar 31, 2010 Jkt 220001 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. The NRC staff has determined that the long-term benefits that will be realized when the PNPP equipment installation is complete, justifies extending the full compliance date with regard to the specified requirement of 10 CFR 73.55. The security measures PNPP needs additional time to implement are new requirements imposed by March 27, 2009, amendments to 10 CFR 73.55, and are in addition to those required by the security orders issued in response to the events of September 11, 2001. Therefore, the NRC 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, deadline for the one item specified in the enclosure of FENOC letter dated November 30, 2009, the licensee is required to be in full compliance by November 25, 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 14638). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 26th day of March 2010. For the Nuclear Regulatory Commission. Joseph G. Giitter, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010–7375 Filed 3–31–10; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0413] Notice of Issuance of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 1.11, Revision 1, ‘‘Instrument Lines Penetrating the Primary Reactor Containment.’’ PO 00000 Frm 00104 Fmt 4703 Sfmt 4703 16525 FOR FURTHER INFORMATION CONTACT: Mekonen M. Bayssie, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone (301) 251– 7489 or e-mail Mekonen.Bayssie@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 1 of Regulatory Guide 1.11, Instrument Lines Penetrating the Primary Reactor Containment,’’ was issued with a temporary identification as Draft Regulatory Guide, DG–1225. This guide defines a basis that the staff of the NRC considers acceptable to implement the intent of General Design Criterion 55 and 56 with regard to instrument lines. This guide applies to light-water-cooled reactors with a primary containment. II. Further Information In September 2009, DG–1225 was published with a public comment period of 60 days from the issuance of the guide. A Summary of the Public Comment Resolution is available through the NRC’s Agencywide Documents Access and Management System (ADAMS) Accession No. ML100250972. Electronic copies of Regulatory Guide 1.11, Revision 1 are available through the NRC’s public Web site under ‘‘Regulatory Guides’’ at https://www.nrc.gov/reading-rm/doccollections/. 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@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. E:\FR\FM\01APN1.SGM 01APN1

Agencies

[Federal Register Volume 75, Number 62 (Thursday, April 1, 2010)]
[Notices]
[Pages 16524-16525]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-7375]


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

NUCLEAR REGULATORY COMMISSION

[Docket No. 50-440; NRC-2010-0124]


FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; 
Exemption

1.0 Background

    FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the 
holder of Facility Operating License No. NFP-58, which authorizes 
operation of the Perry Nuclear Power Plant, Unit 1 (PNPP). The license 
provides, 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 one boiling-water reactor located in Lake 
County, Ohio.

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 includes 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 of these new 
requirements that PNPP 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 30, 2009, as supplemented by letter dated 
December 23, 2009, the licensee requested an exemption in accordance 
with 10 CFR 73.5, ``Specific exemptions.'' The licensee's November 30, 
2009, letter contains proprietary and safeguards information and, 
accordingly, is not available to the public. The licensee has requested 
an exemption from the March 31, 2010, compliance date stating that it 
must complete a significant modification to the current site security 
configuration before all requirements can be met. Specifically, the 
request is for one specific requirement from the current March 31, 
2010, deadline, to November 25, 2010. Being granted this exemption for 
the one item would allow the licensee to complete the modification and 
incorporate state-of-the-art technology to meet or exceed regulatory 
requirements.

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.
    The approval of this exemption, as noted above, would allow an 
extension from March 31, 2010, until November 25, 2010, for one 
specified area of the new rule. As stated above, 10 CFR 73.5 allows the 
NRC to grant exemptions from the requirements of 10 CFR part 73. The 
NRC staff has determined that granting of the licensee's proposed 
exemption would 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 Power Reactor Security provided to the 
Commission, 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

[[Page 16525]]

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 and discussed in the June 4, 2009, letter.

Perry Nuclear Power Plant Schedule Exemption Request

    The licensee provided detailed information in the enclosure of its 
November 30, 2009, letter, requesting an exemption. Enclosure 1 
contains proprietary information regarding the site security plan, 
details of specific portions 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 would enable the licensee to achieve 
full compliance by November 25, 2010. The timeline provides dates 
indicating when (1) Construction will begin on various phases of the 
project, (2) outages are scheduled for the unit, and (3) critical 
equipment will be ordered, installed, tested and become operational.
    Notwithstanding the schedule exemption for this specific 
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 November 25, 2010, PNPP 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 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 with regard to the one specified 
requirement of 10 CFR 73.55 to November 25, 2010.
    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.
    The NRC staff has determined that the long-term benefits that will 
be realized when the PNPP equipment installation is complete, justifies 
extending the full compliance date with regard to the specified 
requirement of 10 CFR 73.55. The security measures PNPP needs 
additional time to implement are new requirements imposed by March 27, 
2009, amendments to 10 CFR 73.55, and are in addition to those required 
by the security orders issued in response to the events of September 
11, 2001. Therefore, the NRC 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, deadline for the one item 
specified in the enclosure of FENOC letter dated November 30, 2009, the 
licensee is required to be in full compliance by November 25, 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 14638).
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 26th day of March 2010.

    For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2010-7375 Filed 3-31-10; 8:45 am]
BILLING CODE 7590-01-P
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