Office of New Reactors; Interim Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment, 13610-13611 [2010-6200]
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Federal Register / Vol. 75, No. 54 / Monday, March 22, 2010 / Notices
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construction methods regarding the
areas in which work is to be performed,
the location of existing infrastructure
such as buried power lines, and/or
unanticipated delays that could
significantly impact the project
schedules. These site-specific safety and
construction methods must be
accounted for in the proposed schedule
that, in turn, impacts the final
compliance date requested. The licensee
has provided a coordinated/combined
schedule for all three projects at SQN
that outlines the sequence in which
work must be conducted to ensure
effective system connectivity. The
required tasks/changes must be
completed in sequence at each site to
support all program upgrades being
performed and to ensure effective
connectivity of each project.
The upgrades that the licensee
identified within their exemption
request support their solution for
meeting the requirements.
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 modifications and the
issues and challenges identified; and is
consistent with the licensee’s requested
compliance date.
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
September 24, 2012, SQN 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 to
September 24, 2012, with regard to two
specified requirements of 10 CFR 73.55.
Accordingly, the Commission has
determined that pursuant to 10 CFR
73.5, the 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 security system upgrades are
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16:41 Mar 19, 2010
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complete justify exceeding the full
compliance date in the case of this
particular licensee. The security
measures SQN 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 staff 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 from the March 31, 2010,
implementation deadline for the two
items specified in Enclosure 1 of the
TVA letter dated November 6, 2009, as
supplemented by letter dated January
11, 2010, the licensee is required to be
in full compliance by September 24,
2012. 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 3762, dated
January 22, 2010).
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 11th 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. 2010–6190 Filed 3–19–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[DC/COL–ISG–020; NRC–2009–0457]
Office of New Reactors; Interim Staff
Guidance on Implementation of a
Seismic Margin Analysis for New
Reactors Based on Probabilistic Risk
Assessment
AGENCY: Nuclear Regulatory
Commission (NRC).
ACTION: Notice of availability.
SUMMARY: The NRC is issuing its Final
Interim Staff Guidance (ISG) DC/COL–
PO 00000
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ISG–020 titled ‘‘Implementation of a
Seismic Margin Analysis for New
Reactors Based on Probabilistic Risk
Assessment,’’ (Agencywide Documents
Access and Management System
(ADAMS) Accession No.
ML100491233). This ISG supplements
the guidance provided to the staff in
Section 19.0 of NUREG–0800, ‘‘Standard
Review Plan for the Review of Safety
Analysis Reports for Nuclear Power
Plants,’’ issued March 2007 and DC/
COL–ISG–03, ‘‘Probabilistic Risk
Assessment Information to Support
Design Certification and Combined
License Applications,’’ dated June 11,
2008 (ADAMS Accession No.
ML081430087) concerning the review of
probabilistic risk assessment (PRA)
information and severe accident
assessments submitted to support
design certification (DC) and combined
license (COL) applications. The NRC
staff intends to incorporate DC/COL–
ISG–020 into the next revision of SRP
Section 19.0 and Regulatory Guide
1.206, ‘‘Combined License Applications
for Nuclear Power Plants (LWR
Edition),’’ June 2007.
Disposition: On October 16, 2009, the
NRC staff issued the proposed ISG, DC/
COL–ISG–020 ‘‘Implementation of a
Seismic Margin Analysis for New
Reactors Based on Probabilistic Risk
Assessment,’’ (ADAMS Accession No.
ML092650316) to solicit public and
industry comment. The NRC staff
received comments on the proposed
guidance. This final issuance
incorporates changes from the majority
of the comments. The NRC staff
responses to these comments can be
found in ADAMS Accession No.
ML100491287.
ADDRESSES: The NRC maintains
ADAMS, which provides text and image
files of NRC’s public documents. These
documents may be accessed through the
NRC’s Public Electronic Reading Room
on the Internet at 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 Public Document Room
reference staff at 1–800–397–4209, 301–
415–4737, or by e-mail at
pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Dr.
Kimberly A. Hawkins, Chief, Structural
Engineering Branch 2, Division of
Engineering, Office of the New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone
at 301–415–0564 or e-mail at
Kimberly.Hawkins@nrc.gov.
E:\FR\FM\22MRN1.SGM
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Federal Register / Vol. 75, No. 54 / Monday, March 22, 2010 / Notices
The
agency posts its issued staff guidance in
the agency external Web page (https://
www.nrc.gov/reading-rm/doccollections/isg/).
SUPPLEMENTARY INFORMATION:
Dated at Rockville, Maryland, this 15th day
of March 2010.
For the Nuclear Regulatory Commission.
William F. Burton,
Chief, Rulemaking and Guidance
Development Branch, Division of New Reactor
Licensing, Office of New Reactors.
[FR Doc. 2010–6200 Filed 3–19–10; 8:45 am]
BILLING CODE 7590–01–P
Dated: March 15, 2010.
Antonio F. Dias,
Chief, Reactor Safety Branch B, Advisory
Committee on Reactor Safeguards.
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS) Planning and
Procedures Subcommittee Meeting;
Notice of Meeting
[FR Doc. 2010–6186 Filed 3–19–10; 8:45 am]
BILLING CODE 7590–01–P
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The ACRS Planning and Procedures
Subcommittee will hold a meeting on
April 7, 2010, at Room T2–B1, at 11545
Rockville Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance, with the exception of
a portion that may be closed pursuant
to 5 U.S.C. 552b(c)(2) and (6) to discuss
organizational and personnel matters
that relate solely to the internal
personnel rules and practices of the
ACRS, and information the release of
which would constitute a clearly
unwarranted invasion of personal
privacy.
The agenda for the subject meeting
shall be as follows:
Wednesday, April 7, 2010,
12 p.m.–1 p.m.
The Subcommittee will discuss
proposed ACRS activities and related
matters. 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 Officer (DFO), Mr. Peter Wen,
(Telephone: 301–415–2832, E-mail:
Peter.Wen@nrc.gov) five days prior to
the meeting, if possible, so that
appropriate arrangements can be made.
Electronic recordings will be permitted
only during those portions of the
meeting that are open to the public.
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
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16:41 Mar 19, 2010
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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
by contacting the 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
the DFO if such rescheduling would
result in major inconvenience.
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS)
Meeting of the ACRS Subcommittee on
Reliability and PRA; Notice of Meeting
The ACRS Reliability and PRA
Subcommittee will hold a meeting on
April 7, 2010, at 11545 Rockville Pike,
T2–B1, Rockville, Maryland.
The entire meeting will be open to
public attendance.
The proposed agenda for the subject
meeting shall be as follows:
Wednesday, April 7, 2010, 8:30 a.m.–
3:30 p.m.
The Subcommittee will update on
staff’s activities to address differences in
various human reliability analysis
models. 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), Peter Wen
(Telephone 301–415–2832, E-mail:
Peter.Wen@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 e-mailed to the DFO one day
before meeting. If an electronic copy
cannot be provided within this
timeframe, presenters should provide
the DFO with a CD containing each
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13611
presentation at least thirty 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 58268–58269).
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 Web site 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 15, 2010.
Antonio F. Dias,
Chief, Reactor Safety Branch B, Advisory
Committee on Reactor Safeguards.
[FR Doc. 2010–6203 Filed 3–19–10; 8:45 am]
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POSTAL REGULATORY COMMISSION
[Docket No. MC2010–20; Order No. 423]
New Postal Product
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
SUMMARY: The Commission is noticing a
recently-filed Postal Service request to
transfer selected Post Office Box Service
locations from the Market Dominant
Product List to the Competitive Product
List. This notice addresses procedural
steps associated with that filing.
DATES: Comments are due: March 31,
2010.
ADDRESSES: Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Commenters who cannot
submit their views electronically should
contact the person identified in the FOR
FURTHER INFORMATION CONTACT section
by telephone for advice on alternatives
to electronic filing.
FOR FURTHER INFORMATION CONTACT:
Stephen L. Sharfman, General Counsel,
202–789–6820 or
stephen.sharfman@prc.gov.
SUPPLEMENTARY INFORMATION:
E:\FR\FM\22MRN1.SGM
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Agencies
[Federal Register Volume 75, Number 54 (Monday, March 22, 2010)]
[Notices]
[Pages 13610-13611]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-6200]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[DC/COL-ISG-020; NRC-2009-0457]
Office of New Reactors; Interim Staff Guidance on Implementation
of a Seismic Margin Analysis for New Reactors Based on Probabilistic
Risk Assessment
AGENCY: Nuclear Regulatory Commission (NRC).
ACTION: Notice of availability.
-----------------------------------------------------------------------
SUMMARY: The NRC is issuing its Final Interim Staff Guidance (ISG) DC/
COL-ISG-020 titled ``Implementation of a Seismic Margin Analysis for
New Reactors Based on Probabilistic Risk Assessment,'' (Agencywide
Documents Access and Management System (ADAMS) Accession No.
ML100491233). This ISG supplements the guidance provided to the staff
in Section 19.0 of NUREG-0800, ``Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear Power Plants,'' issued March 2007
and DC/COL-ISG-03, ``Probabilistic Risk Assessment Information to
Support Design Certification and Combined License Applications,'' dated
June 11, 2008 (ADAMS Accession No. ML081430087) concerning the review
of probabilistic risk assessment (PRA) information and severe accident
assessments submitted to support design certification (DC) and combined
license (COL) applications. The NRC staff intends to incorporate DC/
COL-ISG-020 into the next revision of SRP Section 19.0 and Regulatory
Guide 1.206, ``Combined License Applications for Nuclear Power Plants
(LWR Edition),'' June 2007.
Disposition: On October 16, 2009, the NRC staff issued the proposed
ISG, DC/COL-ISG-020 ``Implementation of a Seismic Margin Analysis for
New Reactors Based on Probabilistic Risk Assessment,'' (ADAMS Accession
No. ML092650316) to solicit public and industry comment. The NRC staff
received comments on the proposed guidance. This final issuance
incorporates changes from the majority of the comments. The NRC staff
responses to these comments can be found in ADAMS Accession No.
ML100491287.
ADDRESSES: The NRC maintains ADAMS, which provides text and image files
of NRC's public documents. These documents may be accessed through the
NRC's Public Electronic Reading Room on the Internet at 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 Public Document Room reference staff at
1-800-397-4209, 301-415-4737, or by e-mail at pdr.resource@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Dr. Kimberly A. Hawkins, Chief,
Structural Engineering Branch 2, Division of Engineering, Office of the
New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone at 301-415-0564 or e-mail at Kimberly.Hawkins@nrc.gov.
[[Page 13611]]
SUPPLEMENTARY INFORMATION: The agency posts its issued staff guidance
in the agency external Web page (https://www.nrc.gov/reading-rm/doc-collections/isg/).
Dated at Rockville, Maryland, this 15th day of March 2010.
For the Nuclear Regulatory Commission.
William F. Burton,
Chief, Rulemaking and Guidance Development Branch, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2010-6200 Filed 3-19-10; 8:45 am]
BILLING CODE 7590-01-P