Indian Point Nuclear Generating Unit Nos. 1, 2, and 3; Exemption, 16872-16874 [2010-7466]
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16872
Federal Register / Vol. 75, No. 63 / Friday, April 2, 2010 / Notices
protection program and provides a
timeline for achieving full compliance
with the new regulation. These plant
modifications are significant in scope
involving the construction of new
facilities, extensive design and
procurement efforts, and work with high
voltage cabling and the personnel safety
risk associated with such work. These
modifications warrant a thorough
review of the safety-security interface
and must be coordinated with BSEP
Unit 1 refueling outage in spring 2010.
All of these efforts require careful
design, planning, procurement, and
implementation efforts. Attachment 1 of
the November 30, 2009, letter contains
security-related information regarding
the site security plan, details of specific
portions of the regulation of which the
site will not be in compliance by the
March 31, 2010, deadline, changes to
the site’s security configuration to meet
the new requirements, and a timeline
(Project Schedule Milestones) with
critical path activities for the licensee to
achieve full compliance by December
20, 2010. The timeline provides dates
indicating when (1) design activities are
completed and approved, (2) the outage
is scheduled for BSEP Unit 1, (3)
construction of a new Security Electrical
Equipment Building begins and is
completed, and (4) the new and
relocated equipment is installed and
tested.
The licensee has provided an
adequate basis for the exemption
request. CP&L identified the physical
protection program components for
which modifications are needed, the
types of modifications and upgrades
needed, as well as construction,
engineering, safety, and infrastructure
considerations which impact the final
compliance date requested. The
required modifications must be
completed in sequence to support all
program upgrades being performed. The
schedule provided by the licensee in
this request outlines the specific tasks
required at BSEP and shows the
sequential order in which work must
proceed with associated dates that
support the requested new compliance
date.
The site-specific information
provided within the BSEP exemption
request is relative to the requirements
from which the licensee requested
exemption and demonstrates the need
for modification to meet the two specific
requirements of 10 CFR 73.55. The
proposed implementation schedule
depicts the critical activity milestones of
the security system upgrades; is
consistent with the licensee’s solution
for meeting the requirements; is
consistent with the scope of the
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16:40 Apr 01, 2010
Jkt 220001
modifications and the issues and
challenges identified and; is consistent
with the licensee’s requested
compliance date.
Notwithstanding the schedule
exemptions for these limited
requirements, 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 NRCapproved physical security program. By
December 20, 2010, BSEP Units 1 and
2 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 with
regard to two specified requirements of
10 CFR 73.55 until December 20, 2010.
Accordingly, the Commission has
determined that pursuant to 10 CFR
73.5, 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 exemptions.
The long-term benefits that will be
realized when these projects are
complete justify extending the March
31, 2010, full compliance date with
regard to the specific requirements of 10
CFR 73.55 for this particular licensee.
The security measures that BSEP 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, 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
exemptions to the March 31, 2010,
deadline for the two items specified in
Attachment 1 of CP&L letter dated
November 30, 2009, the licensee is
required to be in full compliance with
10 CFR 73.55 by December 20, 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
PO 00000
Frm 00154
Fmt 4703
Sfmt 4703
has previously determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (75 FR 8753,
February 25, 2010).
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 25th 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. 2010–7470 Filed 4–1–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–003, 50–247 and 50–286;
NRC–2010–0137]
Indian Point Nuclear Generating Unit
Nos. 1, 2, and 3; Exemption
1.0 Background
Entergy Nuclear Operations, Inc. (the
licensee) is the holder of Facility
Operating License Nos. DPR–5, DPR–26,
and DPR–64, which authorize operation
of the Indian Point Nuclear Generating
Unit Nos. 1, 2, and 3 (IP1, IP2, and IP3).
The licenses provide, among other
things, that the facilities are subject to
all rules, regulations, and orders of the
Nuclear Regulatory Commission (NRC,
the Commission) now or hereafter in
effect.
The facilities consist of one
permanently shut down reactor and two
operating pressurized-water reactors
located in Westchester County in New
York State.
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,
E:\FR\FM\02APN1.SGM
02APN1
Federal Register / Vol. 75, No. 63 / Friday, April 2, 2010 / Notices
mstockstill on DSKH9S0YB1PROD with NOTICES
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 four of these new
requirements that IP1, IP2, and IP3 now
seek 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 January 28, 2010, as
supplemented by letter dated March 8,
2010, the licensee requested an
exemption in accordance with 10 CFR
73.5, ‘‘Specific exemptions.’’ Portions of
the licensee’s letter dated January 28,
2010, contain security-related
information and, accordingly, are
withheld from public disclosure in
accordance with 10 CFR 2.390(d)(1).
The licensee’s supplemental letter dated
March 8, 2010, is withheld in its
entirety as security-related information
in accordance with 10 CFR 2.390(d)(1).
The licensee has requested an
exemption from the March 31, 2010,
compliance date stating that due to
design, procurement, and installation
activities, and in consideration of
impediments to construction such as
winter weather conditions and
equipment delivery schedules,
completion of some of the activities to
facilitate compliance with 10 CFR 73.55
will require additional time beyond
March 31, 2010, before all requirements
can be met. Specifically, the request is
to extend the compliance date for four
specific requirements from the current
March 31, 2010, deadline to February
17, 2011. Being granted this exemption
for the four items would allow the
licensee to complete the modifications
designed to meet the new 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
VerDate Nov<24>2008
16:40 Apr 01, 2010
Jkt 220001
endanger life or property or the common
defense and security, and are otherwise
in the public interest.
This exemption would, as noted
above, allow an extension of compliance
with the new rule from March 31, 2010,
until February 17, 2011, in four specific
areas. 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 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 power reactor
security rule 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 reach full
compliance.
As noted in the final rule, the
Commission also anticipated that
licensees would have to conduct sitespecific analyses to determine what
changes were necessary to implement
the requirements of the rule, 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 request to generically 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.
IP1, IP2, and IP3 Schedule Exemption
Request
The licensee provided detailed
information in a letter dated January 28,
2010, requesting an exemption, as
supplemented by letter dated March 8,
2010. It describes a comprehensive plan
to improve certain physical security
measures, and provides a timeline for
achieving full compliance with the new
regulation. The licensee’s letter dated
January 28, 2010, as supplemented by
letter dated March 8, 2010, contains (1)
PO 00000
Frm 00155
Fmt 4703
Sfmt 4703
16873
security-related information regarding
the site security plan, (2) details of
specific portions of the regulation for
which the site cannot be in compliance
by the March 31, 2010, deadline and the
reasons therefore, (3) the required
changes to the site’s security
configuration, and (4) a timeline with
critical path activities that would enable
the licensee to achieve full compliance
by February 17, 2011. The timeline
provides dates indicating when
construction will begin on various
phases of the project and when critical
equipment will be ordered, installed,
tested and become operational.
Notwithstanding the scheduler
exemptions for these limited
requirements, 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 NRCapproved physical security program. By
February 17, 2011, IP1, IP2, and IP3 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 reviewed the licensee’s
submittals and concludes that the
licensee has justified its request for an
extension of the compliance date with
regard to four specific requirements of
10 CFR 73.55 until February 17, 2011.
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
when the design, procurement, and
installation activities are complete,
justifies extending the full compliance
date in the case of this particular
licensee. The security measures IP1, IP2,
and IP3 need 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 concludes 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 to the March 31, 2010,
E:\FR\FM\02APN1.SGM
02APN1
16874
Federal Register / Vol. 75, No. 63 / Friday, April 2, 2010 / Notices
deadline for the four items specified in
the licensee’s letter dated January 28,
2010, as supplemented by letter dated
March 8, 2010, the licensee is required
to be in full compliance by February 17,
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 14639;
dated March 26, 2010).
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. 2010–7466 Filed 4–1–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
mstockstill on DSKH9S0YB1PROD with NOTICES
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on Radiation
Protection and Nuclear Materials;
Notice of Meeting
The ACRS Subcommittee on
Radiation Protection and Nuclear
Materials will hold a meeting on April
21, 2010, Room T2–B3, at 11545
Rockville Pike, Rockville, Maryland.
The meeting will be open to public
attendance.
The agenda for the subject meeting
shall be as follows:
Wednesday, April 21, 2010–8:30 a.m.–
5 p.m.
The Subcommittee will review
changes to NUREG–1536, ‘‘Standard
Review Plan for Spent Fuel Storage
Systems at a General License Facility.’’
The Subcommittee will hear
presentations by and hold discussions
with NRC staff and other interested
persons regarding this matter. The
Subcommittee will gather information,
analyze relevant issues and facts, and
formulate proposed positions and
actions, as appropriate, for deliberation
by the Full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Christopher L.
VerDate Nov<24>2008
16:40 Apr 01, 2010
Jkt 220001
Brown (telephone: 301–415–7111, email: Christopher.Brown@nrc.gov), five
days prior to the meeting, if possible, so
that appropriate arrangements can be
made. Thirty-five hard copies of each
presentation or handout should be
provided to the DFO thirty minutes
before the meeting. In addition, one
electronic copy of each presentation
should be emailed to the DFO one day
before the meeting. If an electronic copy
cannot be provided within this
timeframe, presenters should provide
the DFO with a CD containing each
presentation at least 30 minutes before
the meeting. Electronic recordings will
be permitted. Detailed procedures for
the conduct of and participation in
ACRS meetings were published in the
Federal Register on October 14, 2009,
(74 FR 52829–52830).
Detailed meeting agendas and meeting
transcripts are available on the NRC
Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information
regarding topics to be discussed,
changes to the agenda, whether the
meeting has been canceled or
rescheduled, and the time allotted to
present oral statements can be obtained
from the website cited above or by
contacting the identified DFO.
Moreover, in view of the possibility that
the schedule for ACRS meetings may be
adjusted by the Chairman as necessary
to facilitate the conduct of the meeting,
persons planning to attend should check
with these references if such
rescheduling would result in major
inconvenience.
Dated: March 29, 2010.
Antonio F. Dias,
Branch Chief, Reactor Safety Branch B,
Advisory Committee on Reactor Safeguards.
[FR Doc. 2010–7455 Filed 4–1–10; 8:45 am]
BILLING CODE 7590–01–P
POSTAL SERVICE
Market Test of ‘‘Samples Co-Op Box’’
Experimental Product
Postal ServiceTM.
ACTION: Notice.
AGENCY:
SUMMARY: The Postal Service gives
notice of a market test of an
experimental product in accordance
with statutory requirements.
DATES: April 2, 2010.
FOR FURTHER INFORMATION CONTACT:
Nabeel Cheema, 202–268–7178.
SUPPLEMENTARY INFORMATION: The
United States Postal Service® hereby
gives notice pursuant to 39 U.S.C.
3641(c)(1) that it will begin a market test
of its ‘‘Samples Co-Op Box’’
PO 00000
Frm 00156
Fmt 4703
Sfmt 4703
experimental product on May 1, 2010.
The Postal Service has filed with the
Postal Regulatory Commission a notice
setting out the basis for the Postal
Service’s determination that the market
test is covered by 39 U.S.C. 3641 and
describing the nature and scope of the
market test. Documents are available at
https://www.prc.gov, Docket No.
MT2010–1.
Stanley F. Mires,
Chief Counsel, Legislative.
[FR Doc. 2010–7507 Filed 4–1–10; 8:45 am]
BILLING CODE 7710–12–P
RAILROAD RETIREMENT BOARD
Proposed Collection; Comment
Request
SUMMARY: In accordance with the
requirement of Section 3506(c)(2)(A) of
the Paperwork Reduction Act of 1995
which provides opportunity for public
comment on new or revised data
collections, the Railroad Retirement
Board (RRB) will publish periodic
summaries of proposed data collections.
Comments are invited on: (a) Whether
the proposed information collection is
necessary for the proper performance of
the functions of the agency, including
whether the information has practical
utility; (b) the accuracy of the RRB’s
estimate of the burden of the collection
of the information; (c) ways to enhance
the quality, utility, and clarity of the
information to be collected; and (d)
ways to minimize the burden related to
the collection of information on
respondents, including the use of
automated collection techniques or
other forms of information technology.
1. Title and purpose of information
collection:
RUIA Investigations and Continuing
Entitlement; OMB 3220–0025.
Under Section 1(k) of the Railroad
Unemployment Insurance Act (RUIA),
unemployment and sickness benefits are
not payable for any day with respect to
which remuneration is payable or
accrues to the claimant. Also Section
4(a–1) of the RUIA provides that
unemployment or sickness benefits are
not payable for any day the claimant
receives the same benefits under any
law other than the RUIA. Under
Railroad Retirement Board (RRB)
regulations, 20 CFR 322.4(a), a
claimant’s certification or statement on
an RRB provided claim form that he or
she did not work on any day claimed
and did not receive income such as
vacation pay or pay for time lost shall
constitute sufficient evidence unless
there is conflicting evidence. Further,
E:\FR\FM\02APN1.SGM
02APN1
Agencies
[Federal Register Volume 75, Number 63 (Friday, April 2, 2010)]
[Notices]
[Pages 16872-16874]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-7466]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-003, 50-247 and 50-286; NRC-2010-0137]
Indian Point Nuclear Generating Unit Nos. 1, 2, and 3; Exemption
1.0 Background
Entergy Nuclear Operations, Inc. (the licensee) is the holder of
Facility Operating License Nos. DPR-5, DPR-26, and DPR-64, which
authorize operation of the Indian Point Nuclear Generating Unit Nos. 1,
2, and 3 (IP1, IP2, and IP3). The licenses provide, among other things,
that the facilities are subject to all rules, regulations, and orders
of the Nuclear Regulatory Commission (NRC, the Commission) now or
hereafter in effect.
The facilities consist of one permanently shut down reactor and two
operating pressurized-water reactors located in Westchester County in
New York State.
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,
[[Page 16873]]
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 four of these new requirements that IP1, IP2, and IP3 now seek 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 January 28, 2010, as supplemented by letter dated
March 8, 2010, the licensee requested an exemption in accordance with
10 CFR 73.5, ``Specific exemptions.'' Portions of the licensee's letter
dated January 28, 2010, contain security-related information and,
accordingly, are withheld from public disclosure in accordance with 10
CFR 2.390(d)(1). The licensee's supplemental letter dated March 8,
2010, is withheld in its entirety as security-related information in
accordance with 10 CFR 2.390(d)(1). The licensee has requested an
exemption from the March 31, 2010, compliance date stating that due to
design, procurement, and installation activities, and in consideration
of impediments to construction such as winter weather conditions and
equipment delivery schedules, completion of some of the activities to
facilitate compliance with 10 CFR 73.55 will require additional time
beyond March 31, 2010, before all requirements can be met.
Specifically, the request is to extend the compliance date for four
specific requirements from the current March 31, 2010, deadline to
February 17, 2011. Being granted this exemption for the four items
would allow the licensee to complete the modifications designed to meet
the new 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.
This exemption would, as noted above, allow an extension of
compliance with the new rule from March 31, 2010, until February 17,
2011, in four specific areas. 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 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 power reactor security rule 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 reach 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 requirements of the rule,
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 request to generically 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.
IP1, IP2, and IP3 Schedule Exemption Request
The licensee provided detailed information in a letter dated
January 28, 2010, requesting an exemption, as supplemented by letter
dated March 8, 2010. It describes a comprehensive plan to improve
certain physical security measures, and provides a timeline for
achieving full compliance with the new regulation. The licensee's
letter dated January 28, 2010, as supplemented by letter dated March 8,
2010, contains (1) security-related information regarding the site
security plan, (2) details of specific portions of the regulation for
which the site cannot be in compliance by the March 31, 2010, deadline
and the reasons therefore, (3) the required changes to the site's
security configuration, and (4) a timeline with critical path
activities that would enable the licensee to achieve full compliance by
February 17, 2011. The timeline provides dates indicating when
construction will begin on various phases of the project and when
critical equipment will be ordered, installed, tested and become
operational.
Notwithstanding the scheduler exemptions for these limited
requirements, 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 February 17, 2011, IP1, IP2, and IP3 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 reviewed the licensee's submittals and concludes that
the licensee has justified its request for an extension of the
compliance date with regard to four specific requirements of 10 CFR
73.55 until February 17, 2011.
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 when the design, procurement, and installation activities
are complete, justifies extending the full compliance date in the case
of this particular licensee. The security measures IP1, IP2, and IP3
need 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 concludes 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 to the March 31, 2010,
[[Page 16874]]
deadline for the four items specified in the licensee's letter dated
January 28, 2010, as supplemented by letter dated March 8, 2010, the
licensee is required to be in full compliance by February 17, 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 14639; dated March 26, 2010).
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. 2010-7466 Filed 4-1-10; 8:45 am]
BILLING CODE 7590-01-P