[Federal Register Volume 77, Number 54 (Tuesday, March 20, 2012)]
[Notices]
[Pages 16271-16278]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2012-6261]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0061]
Biweekly Notice: Applications and Amendments to Facility
Operating Licenses Involving No Significant Hazards Considerations
Background
Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (the
Commission or NRC) is publishing this regular biweekly notice. The Act
requires the Commission publish notice of any amendments issued, or
proposed to be issued and grants the Commission the authority to issue
and make immediately effective any amendment to an operating license
upon a determination by the Commission that such amendment involves no
significant hazards consideration, notwithstanding the pendency before
the Commission of a request for a hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued from February 23 to March 7, 2012. The last
biweekly notice was published on March 6, 2012 (77 FR 13369).
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and is publicly available, by
searching on http://www.regulations.gov under Docket ID NRC-2012-0061.
You may submit comments by the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0061. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: [email protected].
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
Fax comments to: RADB at 301-492-3446.
For additional direction on accessing information and submitting
comments, see ``Accessing Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
SUPPLEMENTARY INFORMATION:
[[Page 16272]]
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2012-0061 when contacting the NRC
about the availability of information regarding this document. You may
access information related to this document, which the NRC possesses
and is publicly available, by the following methods:
Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0061.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. Documents may be viewed in
ADAMS by performing a search on the document date and docket number.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2012-0061 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information in comment submissions that you do not want to be publicly
disclosed. The NRC posts all comment submissions at http://www.regulations.gov as well as entering the comment submissions into
ADAMS, and the NRC does not edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information in their comment submissions
that they do not want to be publicly disclosed. Your request should
state that the NRC will not edit comment submissions to remove such
information before making the comment submissions available to the
public or entering the comment submissions into ADAMS.
Notice of Consideration of Issuance of Amendments to Facility Operating
Licenses, Proposed No Significant Hazards Consideration Determination,
and Opportunity for a Hearing
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Title 10 of the Code of Federal
Regulations (10 CFR) 50.92, this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; (2) create the possibility of a new or different
kind of accident from any accident previously evaluated; or (3) involve
a significant reduction in a margin of safety. The basis for this
proposed determination for each amendment request is shown below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Within 60 days after the date of publication of this notice, any
person(s) whose interest may be affected by this action may file a
request for a hearing and a petition to intervene with respect to
issuance of the amendment to the subject facility operating license.
Requests for a hearing and a petition for leave to intervene shall be
filed in accordance with the Commission's ``Rules of Practice for
Domestic Licensing Proceedings'' in 10 CFR part 2. Interested person(s)
should consult a current copy of 10 CFR 2.309, which is available at
the NRC's PDR, located at One White Flint North, Room O1-F21, 11555
Rockville Pike (first floor), Rockville, Maryland 20852. The NRC's
regulations are accessible online at the NRC Library on the NRC's Web
site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a
request for a hearing or petition for leave to intervene is filed by
the above date, the Commission or a presiding officer designated by the
Commission or by the Chief Administrative Judge of the Atomic Safety
and Licensing Board Panel, will rule on the request and/or petition;
and the Secretary or the Chief Administrative Judge of the Atomic
Safety and Licensing Board will issue a notice of a hearing or an
appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the
[[Page 16273]]
applicant on a material issue of law or fact. Contentions shall be
limited to matters within the scope of the amendment under
consideration. The contention must be one which, if proven, would
entitle the requestor/petitioner to relief. A requestor/petitioner who
fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at http://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with the NRC's guidance
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC's Web site
at http://www.nrc.gov/site-help/e-submittals.html, by email at
[email protected], or by a toll-free call at 1-866-672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852, Attention: Rulemaking and Adjudications Staff. Participants
filing a document in this manner are responsible for serving the
document on all other participants. Filing is considered complete by
first-class mail as of the time of deposit in the mail, or by courier,
express mail, or expedited delivery service upon depositing the
document with the provider of the service. A presiding officer, having
granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
http://ehd1.nrc.gov/ehd/, unless excluded
[[Page 16274]]
pursuant to an order of the Commission, or the presiding officer.
Participants are requested not to include personal privacy information,
such as social security numbers, home addresses, or home phone numbers
in their filings, unless an NRC regulation or other law requires
submission of such information. With respect to copyrighted works,
except for limited excerpts that serve the purpose of the adjudicatory
filings and would constitute a Fair Use application, participants are
requested not to include copyrighted materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Non-timely filings
will not be entertained absent a determination by the presiding officer
that the petition or request should be granted or the contentions
should be admitted, based on a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC PDR Reference staff at 1-800-397-4209,
301-415-4737, or by email to [email protected].
Duke Energy Carolinas, LLC, et al., Docket Nos. 50-413 and 50-414,
Catawba Nuclear Station, Units 1 and 2, York County, South Carolina
Date of amendment request: July 21, 2011.
Description of amendment request: The amendments would revise
Technical Specifications (TSs) 3.3.2, ``Engineered Safety Feature
Actuation System (ESFAS) Instrumentation,'' 3.5.4, ``Refueling Water
Storage Tank (RWST),'' and 3.6.6, ``Containment Spray System.''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes delete superseded TS requirements following
the implementation of NRC approved modifications. As such, they do
not adversely affect accident initiators or precursors nor do they
alter the design assumptions, conditions, or configurations of the
facility. The proposed changes do not alter or prevent the ability
of Structures, Systems, and Components (SSCs) to perform their
intended function to mitigate the consequences of an initiating
event within the assumed acceptance limits. In review of the
discussion above, it can be concluded that the probability or
consequences of any accident previously evaluated will not be
affected.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
This amendment request will not impact the accident analyses.
The proposed changes delete superseded TS requirements following the
implementation of NRC approved modifications. As such, they will not
alter the requirements of any of the subject SSCs or their function
during accident conditions. No new or different accidents will
result from the proposed changes. The changes do not involve a
physical alteration of the plant (i.e., no new or different type of
equipment will be installed) or any changes in methods governing
normal plant operation. The changes do not alter assumptions made in
the safety analyses. The proposed changes are consistent with the
safety analyses assumptions. In review of the discussion above, it
can be concluded that these changes will not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes delete superseded TS requirements following
the implementation of NRC approved modifications. As such, they do
not alter the manner in which safety limits, limiting safety system
settings, or limiting conditions for operation are determined. The
safety analyses acceptance criteria are not affected by these
changes. The proposed changes will not result in plant operation in
a configuration outside the design basis. The proposed changes do
not adversely affect systems that respond to safely shut down the
plant and to maintain the plant in a safe shutdown condition. In
review of the discussion above, it can be concluded that the
proposed changes will not involve a significant reduction in a
margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendments requested involve no significant hazards consideration.
Attorney for licensee: Lara S. Nichols, Associate General Counsel,
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC
28202.
NRC Branch Chief: Nancy Salgado.
Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc.,
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish,
Louisiana
Entergy Nuclear Operations, Inc., Docket Nos. 50-155 and 72-043
(ISFSI), Big Rock Point Plant, Charlevoix County, Michigan
Entergy Nuclear Operations, Inc., Docket Nos. 50-003, 50-247 and
50-286, Indian Point Nuclear Generating Units 1, 2 and 3, Westchester
County, New York
Entergy Nuclear Operations, Inc., Docket No. 50-333, James A.
FitzPatrick Nuclear Power Plant, Oswego County, New York
Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades
Nuclear Plant, Van Buren County, Michigan
Entergy Nuclear Operations, Inc., Docket No. 50-293, Pilgrim Nuclear
Power Station, Plymouth County, Massachusetts
Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations,
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon,
Vermont
Entergy Operations, Inc., Docket Nos. 50-313 and 50-368, Arkansas
Nuclear One, Units 1 and 2, Pope County, Arkansas
Entergy Operations, Inc., System Energy Resources, Inc., South
Mississippi Electric Power Association, and Entergy Mississippi, Inc.,
Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne
County, Mississippi
Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric
Station, Unit 3, St. Charles Parish, Louisiana
Date of amendment request: December 13, 2011.
Description of amendment request: The amendments would approve
changes to the Quality Assurance Program Manual (QAPM) and Technical
Specifications (TSs) for the above specified plants. The proposed
changes standardize unit staff qualification requirements for the
Entergy fleet. Certain changes to the QAPM are a reduction in
commitment and, in accordance with 10 CFR 50.54(a)(4), NRC approval is
required prior to implementation. The related TS changes for unit staff
qualifications are requested in accordance with 10 CFR 50.90.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the
[[Page 16275]]
issue of no significant hazards consideration, which is presented
below:
(1) Does the proposed amendment involve a significant increase
in the probability or consequences of an accident previously
evaluated?
Response: No.
The proposed changes involve the revision or relocation of
administrative requirements associated with unit staff
qualifications and will not impact the design, operation, testing,
performance, or reliability of any plant system or component. The TS
changes will require plants currently required to be qualified per
ANSI [American National Standards Institute] N18.1-1971 to be
qualified to the later standard of ANSI/ANS [American Nuclear
Society] 3.1-1978. The changes do not affect licensed operator
qualifications or training, which will continue to comply with
applicable regulations. Qualification requirements for the Shift
Technical Advisor (STA) are revised to comply with a later standard
that provides more prescriptive qualifications and ensures that the
STA maintains an active status. The changes do not affect operating
procedures or operator response to any accidents previously
evaluated in the Updated Final Safety Analysis Report (UFSAR).
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
(2) Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed amendment is administrative in nature and does not
introduce any credible new failure mechanisms, malfunctions, or
accident initiators. The changes will not alter the plant
configuration, require new plant equipment to be installed, alter
accident analysis assumptions, introduce any new accident
initiators, or affect the function of plant systems or the manner in
which systems are operated, maintained, modified, tested, or
inspected.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
(3) Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment involves the revision or relocation of
administrative requirements associated with unit staff
qualifications. The proposed change is administrative in nature and
does not involve any physical changes to the plant or alter the
manner in which plant systems are operated, maintained, modified,
tested, or inspected. The proposed change does not alter the manner
in which safety limits, limiting safety system settings or limiting
conditions for operation are determined. The safety analysis
acceptance criteria are not affected by this change. The proposed
change will not result in plant operation in a configuration outside
the design basis. The proposed change does not adversely affect
systems that respond to safely shutdown the plant and to maintain
the plant in a safe shutdown condition.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorneys for licensee: Joseph A. Aluise, Associate General
Counsel--Nuclear, Entergy Services, Inc., 639 Loyola Avenue, New
Orleans, LA 70113 (for River Bend Station, Unit 1, Arkansas Nuclear
One, Units 1 and 2, Grand Gulf Nuclear Station, Unit 1, and Waterford
Steam Electric Station, Unit 3); and William C. Dennis, Assistant
General Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue,
White Plains, NY 10601 (for Big Rock Point Plant (ISFSI), James A.
Fitzpatrick Nuclear Power Plant, Indian Point Nuclear Generating Units
1, 2, and 3, Palisades Nuclear Plant, Pilgrim Nuclear Power Station,
and Vermont Yankee Nuclear Power Station).
NRC Branch Chief: Michael T. Markley.
Notice of Issuance of Amendments to Facility Operating Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license, proposed no significant hazards consideration
determination, and opportunity for a hearing in connection with these
actions, was published in the Federal Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection at
the NRC's Public Document Room (PDR), located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible online through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by email to
[email protected].
Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of application for amendment: August 12, 2011, supplemented by
letter dated October 20, 2011.
Brief description of amendment: The amendment revised TS 3.8.3,
``Diesel Fuel Oil and Starting Air,'' by relocating the current stored
diesel fuel oil numerical volume requirements from the Technical
Specification to the TS Bases consistent with Technical Specification
Task Force TSTF-501.
Date of issuance: February 24, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment No.: 188.
Facility Operating License No. NPF-43: Amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: October 4, 2011 (76 FR
61394).
The supplemental letter dated October 20, 2011 did not change
staff's original proposed no significant hazards consideration
determination as published in the initial Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 24, 2012.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-373, LaSalle County
Station, Unit 1, LaSalle County, Illinois
[[Page 16276]]
Date of application for amendment: October 12, 2011, as
supplemented by letter(s) dated January 30, 2012, and February 13,
2012.
Brief description of amendment: The amendment request proposed
changes to the Technical Specifications (TSs) to revise Section 2.1.1,
``Reactor Core SLs'' minimum critical power ratio safety limit (MCPR
SL) from >= 1.11 to >= 1.13 for two-loop recirculation operation and
from >= 1.12 to >= 1.15 for a single-loop recirculation operation.
Date of issuance: March 1, 2012.
Effective date: As of the date of issuance and shall be implemented
after Cycle 14 is completed and prior to the operation of Cycle 15.
Amendment No.: 205.
Facility Operating License Nos. NPF-11: The amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: January 3, 2012 (77 FR
139).
The January 30, 2012, and February 13, 2012, supplements contained
clarifying information, did not expand the scope of the application as
originally noticed, and did not change the staff's original proposed no
significant hazards consideration (NSHC) determination.
The Commission's related evaluation of the amendment and final NSHC
determination is contained in a Safety Evaluation dated March 1, 2012.
No significant hazards consideration comments received: No.
Florida Power and Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Plant, Units 3 and 4, Miami-Dade County, Florida
Date of application for amendment: February 21, 2011, as
supplemented by letter dated July 21, 2011.
Brief description of amendment: Selected figures and values from
the technical specifications (TSs) are being relocated to the Core
Operating Limits Report (COLR), including TS Figure 2.1-1 cited in TS
2.1.1, selected portions of Note 1 on Overtemperature [Delta] T and
Note 3 on Overpower [Delta] T cited in TS Table 2.2-1, TS Figure 3.1-1
cited in TS 3/4.1.1.1, Shutdown Margin value cited in TS 3/4.1.1.2,
Moderator Temperature Coefficient values cited in TS 3/4.1.1.3, and
Departure from Nucleate Boiling values cited in TS 3.2.5. The
description of the COLR in TS 6.9.1.7 is also revised to reflect these
changes. The affected TS figures and technical limits cited above are
only being relocated to the COLR and are not being changed under this
license amendment.
Date of issuance: February 23, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: Unit 3--247 and Unit 4--243.
Renewed Facility Operating License Nos. DPR-31 and DPR-41:
Amendments revised the Technical Specifications and Surveillance
Requirements.
Date of initial notice in Federal Register: May 31, 2011 (76 FR
31374). The supplement dated July 21, 2011, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the staff's
original proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 23, 2012.
No significant hazards consideration comments received: No.
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold
Energy Center, Linn County, Iowa
Date of application for amendment: February 23, 2011, as
supplemented by letters dated April 20, August 15, November 1, 2011,
and February 3, 2012.
Brief description of amendment: The amendment revised the Technical
Specifications (TSs) by relocating specific surveillance frequencies to
a licensee-controlled program with the guidance of Nuclear Energy
Institute (NEI) 04-10, ``Risk-Informed Technical Specifications
Initiative 5b, Risk-Informed Method for Control of Surveillance
Frequencies.'' The amendment adopted NRC-approved Technical
Specification Task Force (TSTF)-425, Revision 3, ``Relocate
Surveillance Frequencies to Licensee Control--RITSTF [Risk-Informed
TSTF] Initiative 5b.'' When implemented, TSTF-425 relocates most
periodic frequencies of TS surveillances to a licensee-controlled
program, the Surveillance Frequency Control Program, and provides
requirements for the new program in the Administrative Controls section
of the TSs.
Date of issuance: February 24, 2012.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment No.: 280.
Renewed Facility Operating License No. DPR-49: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: May 17, 2011 (76 FR
28474).
The supplemental letters dated April 20, August 15, November 1,
2011 and February 3, 2012, provided additional information that
clarified the application, did not expand the scope of the application
as originally noticed, and did not change the staff's original proposed
no significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 24, 2012.
No significant hazards consideration comments received: No.
NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit
1, Rockingham County, New Hampshire
Date of amendment request: April 21, 2011.
Description of amendment request: The amendment revised operability
requirements for the leakage detection systems, eliminated redundant
Technical Specification (TS) requirements, and revised the TS actions
to include conditions and required actions for inoperable leakage
detection systems similar to those in NUREG 1431, ``Standard Technical
Specifications--Westinghouse Plants.'' The amendment also incorporated
the requirements of TSTF-513, Revision 3, ``Revise [Pressurized Water
Reactor] Operability Requirements and Actions for [Reactor Coolant
System] Leakage Instrumentation.''
Date of issuance: February 23, 2012.
Effective date: As of its date of issuance and shall be implemented
within 90 days.
Amendment No.: 129.
Facility Operating License No. NPF-86: The amendment revised the TS
and the License.
Date of initial notice in Federal Register: August 9, 2011 (76 FR
48913).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 23, 2012.
No significant hazards consideration comments received: No.
NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit
1, Rockingham County, New Hampshire
Date of amendment request: November 17, 2011.
Description of amendment request: The proposed change revises
Technical Specification 3.3.3.5, ``Remote Shutdown System Table 3.3-
9,'' by removing the location information of transfer switches, control
circuits, and instruments.
Date of issuance: February 28, 2012.
Effective date: As of its date of issuance and shall be implemented
within 30 days.
Amendment No.: 130.
[[Page 16277]]
Facility Operating License No. NPF-86: The amendment revised the TS
and the License.
Date of initial notice in Federal Register: December 27, 2011 (76
FR 80976).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 28, 2012.
No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, South Carolina Public Service
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit 1,
Fairfield County, South Carolina
Date of application for amendment: May 2, 2011.
Brief description of amendment: This license amendment revised the
Technical Specifications (TSs) 3.4.6.1, ``RCS [Reactor Coolant System]
Leakage Detection Systems,'' to define a new time limit for restoring
inoperable RCS leakage detection instrumentation to operable status,
establish alternate methods of monitoring RCS leakage when monitors are
inoperable, and to reflect the requested changes and more accurately
reflect the contents of the facility design bases related to the
operability of the RCS leakage detection instrumentation.
Date of issuance: February 22, 2012.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment No.: 186.
Renewed Facility Operating License No. NPF-12: Amendment revises
the License and TSs.
Date of initial notice in Federal Register: July 12, 2011 (76 FR
40941).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 22, 2012.
No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket No. 50-395, Virgil C.
Summer, Nuclear Station Unit 1, Jenkinsville, South Carolina
Date of application for amendment: April 18, 2011, and supplemented
by letter dated September 26, 2011.
Brief description of amendment: This amendment revised the VCSNS
Technical Specification Table 4.3-2 for the ``Engineered Safety Feature
Actuation System Instrumentation'' to allow the surveillance frequency
to be expanded from quarterly to every 18 months or refueling for the
specific Westinghouse type AR relays used as Solid State Protection
System slave relays or auxiliary relays.
Date of Issuance: March 6, 2012.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment No: 187.
Renewed Facility Operating License No. NPF-12: Amendment revised
the Licenses and Technical Specifications.
Date of initial notice in Federal Register: August 16, 2011 (76 FR
50763).
The licensee's supplemental letter contained clarifying
information, did not change the scope of the original license amendment
request, did not change the NRC staff's initial proposed finding of no
significant hazards consideration determination, and did not expand the
scope of the original Federal Register notice.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 6, 2012.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County,
Georgia
Date of application for amendment: March 3, 2011.
Brief description of amendment: The amendments revised the
Technical Specifications (TS) 3.3.1 Reactor Trip System Instrumentation
Table 3.3.1-1 and TS 3.3.2 Emergency System Feature Actuation System
Table 3.3.2-1. Specifically, the change incorporates the Technical
Specification Task Force Traveler TSTF-493-A, ``Clarify Application of
Setpoint Methodology for LSSS [limiting safety system setting]
Function. The setpoint methodology incorporates revised (more
conservative) calculations associated with the P-14, Steam Generator
Water Level High-High instrument setpoint and associated allowable
value. Also, the amendments contain administrative changes.
Specifically, the amendment correct a typographical error on TS Table
3.3.1-1, page 9 of 9, and deletes an expired allowance provided by TS
Table 3.3.2-1, Note J.
Date of issuance: February 27, 2012.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos.: Unit 1--165 and Unit 2--147.
Facility Operating License Nos. NPF-68 and NPF-81: Amendments
revised the licenses and the technical specifications.
Date of initial notice in Federal Register: May 24, 2011 (re-
noticed on July 12, 2011).
The supplements dated August 12, 2011, and December 9, 2011,
provided additional information that clarified the application, did not
expand the scope of the application as originally noticed, and did not
change the staff's original proposed no significant hazards
consideration determination.
The Commission's related evaluation of the amendments is contained
in Safety Evaluation dated February 27, 2012.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339,
North Anna Power Station, Units 1 and 2, Louisa County, Virginia
Date of application for amendment: July 19, 2010, and supplemented
by additional information dated September 9, 2010, January 26, 2011,
and May 16, 2011, contained clarifying information only and did not
change the initial no significant hazards determination or expand the
scope of the initial application.
Brief description of amendment: The proposed amendments revise
Technical Specification 5.6.5.b, ``Core Operating Limits Report
(COLR),'' to include Appendix C, ``Qualification of the Westinghouse
WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code.'' This
would allow NAPS to use the VIPRE-D/WRB-2M and VIPRE-D/W-3 correlation
pairs to perform licensing calculations with Westinghouse RFA-2 fuel in
the cores.
Date of issuance: February 29, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment Nos.: Unit 1--266 and Unit 2--247.
Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments
changed the licenses and the technical specifications.
Date of initial notice in Federal Register: July 26, 2011 (76 FR
44618).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 29, 2012.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339,
North Anna Power Station, Units 1 and 2, Louisa County, Virginia
Date of application for amendment: October 21, 2010, as
supplemented by letter dated June 23, 2011, and August 22, 2011,
contained clarifying information only and did not change the initial no
significant hazards determination or expand the scope of the initial
application.
[[Page 16278]]
Brief description of amendment: The proposed amendments revised
Technical Specification 5.6.5.b, ``Core Operating Limits Report
(COLR),'' to permit the use of the ``Westinghouse Best Estimate--Large
Break Loss-of-Coolant Accident (BE-LBLOCA) Evaluation Methodology using
the Automated Statistical Treatment of Uncertainty Method (ASTRUM)''
for the analysis of LBLOCA.
Date of issuance: February 29, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment Nos.: Unit 1--267 and Unit 2--248.
Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments
changed the licenses and the technical specifications.
Date of initial notice in Federal Register: November 30, 2010 (75
FR 74097).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated February 29, 2012.
No significant hazards consideration comments received: No.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 8th day of March 2012.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2012-6261 Filed 3-19-12; 8:45 am]
BILLING CODE 7590-01-P