Biweekly Notice, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 11688-11699 [2013-03582]
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11688
Federal Register / Vol. 78, No. 33 / Tuesday, February 19, 2013 / Notices
Dated at Rockville, Maryland, this 12th day
of February 2013.
For the Nuclear Regulatory Commission.
Tremaine Donnell,
NRC Clearance Officer, Office of Information
Services.
[FR Doc. 2013–03721 Filed 2–15–13; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Notice of Issuance of Amendment to
Facility License R–77 Incorporating a
Decommissioning Plan for the Buffalo
Materials Research Center Reactor at
the State University of New York at
Buffalo
Nuclear Regulatory
Commission.
ACTION: Notice of issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has approved the
State University of New York at Buffalo
(UB) decommissioning plan (DP) by
amendment to the Facility License R–77
for the Buffalo Materials Research
Center (BMRC) reactor.
FOR FURTHER INFORMATION CONTACT:
Theodore Smith, Project Manager,
Office of Federal and State Materials
and Environmental Management
Programs, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–6721; email:
Theodore.Smith@nrc.gov
SUMMARY:
Please refer to Docket ID
NRC–2012–0103 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 are publicly-available,
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0103. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–492–3668;
email: Carol.Gallagher@nrc.gov.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/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 at PDR.Resource@nrc.gov. The
ADAMS accession number for each
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ADDRESSES:
17:49 Feb 15, 2013
For the Nuclear Regulatory Commission.
Andrew Persinko,
Deputy Director Decommissioning and
Uranium Recovery, Licensing Directorate,
Division of Waste Management and
Environmental Protection, Office of Federal
and State Materials, and Environmental
Management Programs.
[FR Doc. 2013–03762 Filed 2–15–13; 8:45 am]
BILLING CODE 7590–01–P
I. Notice of Issuance
[Docket No. 50–57; NRC–2012–0103]
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document referenced in this notice (if
that document is available in ADAMS)
is provided the first time that the
document is referenced.
• 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.
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The BMRC reactor is located at the UB
in Buffalo, NY. The reactor is a
PULSTAR heterogeneous open-pool
type water cooled reactor. The reactor
operated from March 24, 1961 until June
23, 1994. During operation, the reactor
used 6% enriched uranium dioxide fuel
clad in zirconium-alloy. The UB
submitted the DP for the reactor to the
NRC in a letter dated February 17, 2012
(ADAMS accession no. ML120540187),
as supplemented by letters dated June
20, 2012 (ADAMS accession no.
ML121870132), September 21, 2012
(ADAMS accession no. ML122780454),
and October 15, 2012 (ADAMS
accession no. ML12297A237).
Pursuant to sections 20.1405 and
50.82(b)(5) of Title 10 of the Code of
Federal Regulations (10 CFR), the NRC
published a notice and solicitation of
comments for this DP in the Federal
Register entitled, ‘‘License Amendment
Request From The State University of
New York, University of Buffalo Reactor
Facility,’’ on May 10, 2012 (77 FR
27487). No comments were received in
response to this notice.
Subsequently, the NRC conducted a
safety evaluation of the proposed DP
(ADAMS accession no. ML12286A352).
Based on this safety evaluation, the NRC
concluded that, pursuant to 10 CFR
50.82(b)(5), the DP demonstrates that
the proposed decommissioning will be
performed in accordance with the
Commission’s regulations and will not
be inimical to the common defense and
security or to the health and safety of
the public. Therefore, the Commission
approved, by amendment to Facility
License R–77, the DP subject to the
safety evaluation.
The NRC is publishing this notice
announcing the issuance of the
amendment to Facility License R–77
pursuant to 10 CFR 2.106(a)(1), because
a notice of proposed action regarding
this amendment had been previously
published.
Dated at Rockville, Maryland, this 11th day
of February, 2013.
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NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0032]
Biweekly Notice, Applications and
Amendments to Facility Operating
Licenses and Combined 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 (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 or combined
license, as applicable, 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 January 24,
2013, to February 6, 2013. The last
biweekly notice was published on
February 5, 2013 (78 FR 8195).
ADDRESSES: You may access information
and comment submissions related to
this document, which the NRC
possesses and are publically available,
by searching on https://
www.regulations.gov under Docket ID
NRC–2013–0032. You may submit
comments by any of the following
methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0032. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–492–3668;
email: Carol.Gallagher@nrc.gov.
• 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.
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Federal Register / Vol. 78, No. 33 / Tuesday, February 19, 2013 / Notices
• 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:
I. Accessing Information and
Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC–2013–
0032 when contacting the NRC about
the availability of information regarding
this document. You may access
information related to this document by
any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0032.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/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 pdr.resource@nrc.gov.
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.
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B. Submitting Comments
Please include Docket ID NRC–2013–
0032 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 that
that you do not want to be publicly
disclosed in your comment submission.
The NRC will post all comment
submissions at https://
www.regulations.gov as well as enter the
comment submissions into ADAMS.
The NRC does not routinely 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 that
they do not want to be publicly
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17:49 Feb 15, 2013
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disclosed in their comment submission.
Your request should state that the NRC
does not routinely 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 and Combined 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
Section 50.92 of Title 10 of the Code of
Federal Regulations (10 CFR), 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; or (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 60day 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.
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11689
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 or
combined license. Requests for a
hearing and a petition for leave to
intervene shall be filed in accordance
with the Commission’s ‘‘Agency Rules
of Practice and Procedures’’ 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 regulations are accessible
electronically from the NRC Library on
the NRC’s Web site at https://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
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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
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 the 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 EFiling 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
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participant should contact the Office of
the Secretary by email at
hearing.docket@nrc.gov, 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 NRCissued 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 https://
www.nrc.gov/site-help/e-submittals/
apply-certificates.html. System
requirements for accessing the ESubmittal server are detailed in the
NRC’s ‘‘Guidance for Electronic
Submission,’’ which is available on the
agency’s public Web site at https://
www.nrc.gov/site-help/esubmittals.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 Webbased submission form, including the
installation of the Web browser plug-in,
is available on the NRC’s public Web
site at https://www.nrc.gov/site-help/esubmittals.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 https://www.nrc.gov/sitehelp/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
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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 EFiling 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 Web site at https://
www.nrc.gov/site-help/esubmittals.html, by email at
MSHD.Resource@nrc.gov, or by a tollfree 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
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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 https://
ehd1.nrc.gov/ehd/, unless excluded
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.
Requests for hearing, petitions for leave
to intervene, and motions for leave to
file new or amended contentions that
are filed after the 60-day deadline will
not be entertained absent a
determination by the presiding officer
that the filing demonstrates good cause
by satisfying the following three factors
in 10 CFR 2.309(c)(1): (i) The
information upon which the filing is
based was not previously available; (ii)
the information upon which the filing is
based is materially different from
information previously available; and
(iii) the filing has been submitted in a
timely fashion based on the availability
of the subsequent information.
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 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’s PDR
Reference staff at 1–800–397–4209, 301–
415–4737, or by email to
pdr.resource@nrc.gov.
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Carolina Power and Light Company, et
al., Docket No. 50–400, Shearon Harris
Nuclear Power Plant, Unit 1, Wake
County, North Carolina
Date of amendment request:
November 29, 2012, as supplemented by
letter dated January 3, 2013.
Description of amendment request:
The amendment revised the Technical
Specification (TS) surveillance
requirements for addressing a missed
surveillance, and is consistent with the
U.S. Nuclear Regulatory Commission
approved Revision 6 of Technical
Specification Task Force (TSTF)
Standard TSs Change Traveler TSTF–
358, ‘‘Missed Surveillance
Requirements.’’
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 change involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The proposed change revises the Technical
Specifications (TS) Table 3.3–4, Functional
Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage—
Secondary time delay values. The Loss of
Offsite Power, 6.9 kV (kilovolt) Emergency
Bus Undervoltage—Secondary
instrumentation functions are not initiators
to any accident previously evaluated. As
such, the probability of an accident
previously evaluated is not increased. The
revised values continue to provide
reasonable assurance that the Loss of Offsite
Power, 6.9 kV (kilovolt) Emergency Bus
Undervoltage—Secondary function will
continue to perform its intended safety
functions. As a result, the proposed change
will not increase the consequences of an
accident previously evaluated.
Concurrent with this proposed change, the
Harris Nuclear Plant is revising its large
break loss of coolant accident analysis. The
revised analysis will be evaluated in
accordance with 10 CFR 50.59 to confirm
that a change to the technical specifications
incorporated in the license is not required,
and the change does not meet any of the
criteria in Paragraph (c)(2) of that regulation.
The revised analysis will employ the plantspecific methodology ANP–3011(P), Harris
Nuclear Plant, Unit 1, Realistic Large Break
LOCA Analysis, Revision 1, as approved by
NRC Safety Evaluation dated May 30, 2012.
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.
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The proposed change revises the Technical
Specification (TS) Table 3.3–4, Functional
Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage—
Secondary time delay values. No new
operational conditions beyond those
currently allowed are introduced. This
change is consistent with the safety analyses
assumptions and current plant operating
practices. This simply corrects the setpoint
consistent with the accident analyses and
therefore cannot create the possibility of a
new or different kind of accident from any
previously evaluated accident.
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 change involve a
significant reduction in the margin of safety?
Response: No.
The proposed change revises the Technical
Specifications (TS) Table 3.3–4, Functional
Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage—
Secondary time delay values. This proposed
change implements a reduced time delay to
isolate safety buses from offsite power if a
Loss of Coolant Accident were to occur
coincident with a sustained degraded voltage
condition. This provides improved margin to
ensure that emergency core cooling system
pumps inject water into the reactor vessel
within the time assumed and evaluated in
the accident analysis.
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.
Attorney for licensee: David T.
Conley, Manager—Senior Counsel—
Legal Department, Progress Energy
Service Company, LLC, Post Office Box
1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Jessie F.
Quichocho.
Duke Energy Carolinas, LLC, Docket
Nos. 50–269, 50–270, and 50–287,
Oconee Nuclear Station, Units 1, 2, and
3 (ONS1, ONS2, and ONS3), Oconee
County, South Carolina
Date of amendment request: October
30, 2012.
Description of amendment request:
The proposed amendment would revise
the Technical Specifications (TSs) to
specify that TS 3.8.1 Required Action
(RA) C.2.2.5 is cumulative over a 3-year
time period for each Keowee
Hydroelectric Unit (KHU). The two
KHUs serve as the emergency power
supply for ONS1, ONS2, and ONS3. RA
C.2.2.5 currently allows a 45-day
Completion Time once every 3 years to
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restore an inoperable KHU to service.
This revision would allow the 45-day
Completion Time to be used as a
cumulative allowance over 3 years,
rather than once every 3 years. This
Completion Time is used for major
Keowee Hydroelectric Unit (KHU)
maintenance.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
licensee provided its analysis of the
issue of no significant hazards
consideration, which is presented
below:
1. Does the proposed change involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The proposed amendment adds a note to
the 45-day Completion Time for Technical
Specification (TS) 3.8.1 Required Action (RA)
C.2.2.5 to clarify the 45 days is cumulative
for each Keowee Hydroelectric Unit (KHU)
over a rolling 3-year time period rather than
limited to one continuous 45-day time
period. During the time that one KHU is
inoperable for > 72 hours, a Lee Combustion
Turbine (LCT) will be energizing both
standby buses, two offsite power sources will
be maintained available, and maintenance on
electrical distribution systems will not be
performed unless necessary.
There is no adverse impact on containment
integrity, radiological release pathways, fuel
design, filtration systems, main steam relief
valve set points, or radwaste systems. No
new radiological release pathways are
created.
The consequences of an event occurring
during the modified 45-day Completion
Time, which clarifies the 45 days is
cumulative for each KHU over a rolling 3year time period, are the same as those that
would occur during a continuous 45-day
Completion Time. Duke Energy reviewed the
Probabilistic Risk Assessment (PRA) to gain
additional insights concerning the
configuration of ONS with one KHU
inoperable for one continuous 45 day period
versus multiple time periods totally [totaling]
45-days. Based on this review, Duke Energy
concluded that there is no change in risk.
Therefore, the probability or consequences
of an accident previously evaluated is not
significantly increased.
2. Does the proposed change create the
possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
The proposed amendment adds a note to
the 45-day Completion Time for TS 3.8.1
Required Action C.2.2.5 to clarify the 45 days
is cumulative for each KHU over a rolling 3year time period rather than limited to one
continuous 45-day time period. During the
time period that one KHU is inoperable and
the 45-day Completion Time is being
applied, the redundancy requirement for the
emergency power source will be fulfilled by
an LCT [Lee Combustion Turbine] and other
compensatory measures required by TS 3.8.1
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RA C.2.2.1, C.2.2.2, C.2.2.3, and C.2.2.4 will
be in place to minimize electrical power
system vulnerabilities.
The proposed change to the 45-day
Completion Time does not involve a physical
effect on the Oconee Units, nor is there any
increased risk of an Oconee Unit trip or
reactivity excursion. No new failure modes or
credible accident scenarios are postulated
from this activity.
Therefore, the possibility of a new or
different kind of accident from any kind of
accident previously evaluated is not created.
3. Does the proposed change involve a
significant reduction in a margin of safety?
Response: No.
The proposed amendment adds a note to
the 45-day Completion Time for TS 3.8.1 RA
C.2.2.5 to clarify the 45 days is cumulative
for each KHU over a rolling 3-year time
period rather than limited to one continuous
45-day time period. During the time period
that one KHU is inoperable and the 45-day
Completion Time is being applied, the
redundancy requirement for the emergency
power source will be fulfilled by an LCT and
other compensatory measures required by TS
3.8.1 RA C.2.2.1, C.2.2.2, C.2.2.3, and C.2.2.4
will be in place to minimize electrical power
system vulnerabilities.
The proposed TS change does not involve:
1) a physical alteration of the Oconee Units;
2) the installation of new or different
equipment; 3) operating any installed
equipment in a new or different manner; 4)
a change to any set points for parameters
which initiate protective or mitigation action;
or 5) any impact on the fission product
barriers or safety limits.
Therefore, this request 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.
Attorney for licensee: Lara S. Nichols,
Associate General Counsel, Duke Energy
Corporation, 526 South Church Street—
EC07H, Charlotte, NC 28202–1802.
NRC Branch Chief: Robert J.
Pascarelli.
Florida Power and Light Company,
Docket Nos. 50–250 and 50–251, Turkey
Point Nuclear Generating Units 3 and 4,
Miami-Dade County, Florida
Date of amendment request: October
30, 2012.
Description of amendment request:
The proposed amendments would
decrease the time limits in certain
actions and surveillance requirements of
Technical Specification (TS) 3.5.2,
‘‘ECCS [emergency core cooling system]
Subsystems,’’ and revise certain
footnotes of TS 3.5.2 for clarity.
Basis for proposed no significant
hazards consideration determination:
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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?
No. The proposed amendment does not
change or modify the design or operation of
ECCS systems, subsystems, or components.
The proposed amendment does not affect any
precursors to any accident previously
evaluated or do not adversely affect known
mitigation equipment or strategies. The
proposed amendment provides better
assurance that the ECCS systems,
subsystems, and components are properly
aligned to support safe reactor operation
consistent with the licensing and design
basis requirements. The proposed changes
addressing cascading of emergency power
requirements are considered non-intent
changes. Therefore, the proposed amendment
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?
No. The proposed amendment provides
better assurance that the ECCS systems,
subsystems, and components are properly
aligned to support safe reactor operation
consistent with the licensing and design
basis requirements. No new accident
initiators are introduced directly or indirectly
by the proposed changes. The changes
addressing cascading of emergency power
requirements are considered non-intent
changes. Therefore, the proposed amendment
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 the margin of
safety?
No. The proposed amendment provides
better assurance that the ECCS systems,
subsystems, and components are properly
aligned to support safe reactor operation
consistent with the licensing and design
basis requirements. The proposed changes
correct deficiencies regarding TS LCO
[limiting condition for operation] 3.5.2.d and
TS SR [surveillance requirement] 4.5.2.a to
assure ECCS availability is maintained
within the assumptions of the safety analysis.
Therefore, the proposed amendment does not
involve a significant reduction in the margin
of safety.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 50.92(c) are satisfied.
Therefore, the NRC staff proposes to
determine that the amendment request
involves no significant hazards
consideration.
Attorney for licensee: James Petro,
Managing Attorney—Nuclear, Florida
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Power & Light, P.O. Box 14000, Juno
Beach, Florida 33408–0420.
NRC Branch Chief: Jessie F.
Quichocho.
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Southern Nuclear Operating Company
Docket Nos. 52–025 and 52–026, Vogtle
Electric Generating Plant (VEGP) Units
3 and 4, Burke County, Georgia
Date of amendment request:
December 7, 2012, and revised on
January 25, 2013.
Description of amendment request:
The proposed change would amend
Combined License Nos. NPF–91 and
NPF–92 for Vogtle Electric Generating
Plant (VEGP) Units 3 and 4 in regard to
the Primary Sampling System (PSS) by:
(1) replacing containment air return
check valve PSS–PL–V024 with a
solenoid-operated valve, and (2)
redesigning the PSS inside-containment
header and adding a PSS containment
penetration.
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 Primary Sampling System (PSS)
provides the safety-related function of
preserving containment integrity by isolation
of the PSS lines penetrating containment.
The proposed amendment will enhance the
ability of the PSS to perform its nonsafetyrelated function of providing the capability to
obtain reactor coolant and containment
atmosphere samples, while maintaining the
ability of the PSS to perform its safety-related
containment isolation function. The
replacement of a check valve with a solenoidoperated containment isolation valve and the
redesigned inside-containment header does
not affect the safety-related function of
isolating the PSS lines for containment
isolation. The components added by this
proposed activity, including tubing and the
solenoid-operated containment isolation
valve, are designed to the same codes and
standards as other components addressed in
the certified design that perform similar
functions. The additional PSS containment
penetration is a passive extension of
containment and is identical in form, fit, and
function to other PSS sampling containment
penetrations currently addressed in the
certified AP1000 plant design. The addition
of a new PSS containment penetration will
not change the maximum allowable leakage
rate allowed by Technical Specifications and
verified periodically in accordance with
regulations. Furthermore, the proposed PSS
configuration changes will neither impact
any accident source term parameter or fission
product barrier nor affect radiological dose
consequence analysis.
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Therefore, the proposed amendment 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 additional containment penetration is
similar in form, fit, and function to the PSS
penetrations that are currently described in
the Updated Final Safety Analysis Report.
Because the PSS changes use valve types,
piping, and a containment penetration
consistent with those already described in
the Updated Final Safety Analysis Report, no
new failure modes or equipment failure
initiators are introduced by these changes.
Accordingly, the proposed changes do not
create any new malfunctions, failure
mechanisms, or accident initiators.
Therefore, the proposed amendment 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 containment isolation function is not
changed by this activity and is bounded by
the existing design. The proposed PSS
containment penetration is similar in form,
fit, and function to other containment
penetrations in similar applications in the
current certified AP1000 plant design. The
additional PSS containment penetration is an
extension of containment, and, therefore,
does not affect containment or its ability to
perform its design function. The addition of
PSS components, including the solenoidoperated containment isolation valve, the
additional PSS containment penetration, and
the associated tubing, do not exceed or alter
a design basis or safety limit. Because the
containment isolation function, containment
leakage rate limit, potential containment
leakage, and protective shielding are not
changed by this activity and are bounded by
the existing design, there is no change to any
current margin of safety.
Therefore, the proposed amendment 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.
Attorney for licensee: Mr. M. Stanford
Blanton, Balch & Bingham LLP, 1710
Sixth Avenue North, Birmingham, AL
35203–2015.
NRC Acting Branch Chief: Lawrence
Burkhart.
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11693
Previously Published Notices of
Consideration of Issuance of
Amendments to Facility Operating
Licenses and Combined Licenses,
Proposed No Significant Hazards
Consideration Determination, and
Opportunity for a Hearing
The following notices were previously
published as separate individual
notices. The notice content was the
same as above. They were published as
individual notices either because time
did not allow the Commission to wait
for this biweekly notice or because the
action involved exigent circumstances.
They are repeated here because the
biweekly notice lists all amendments
issued or proposed to be issued
involving no significant hazards
consideration.
For details, see the individual notice
in the Federal Register on the day and
page cited. This notice does not extend
the notice period of the original notice.
Florida Power and Light Company,
Docket Nos. 50–250 and 50–251, Turkey
Point Generating Units 3 and 4, MiamiDade County, Florida
Date of application for amendments:
September 6, 2012.
Description of amendments request:
The proposed amendments would
reduce the minimum sodium tetraborate
basket loading to 7500 pounds mass in
order to lessen the long term sump pH
profile, recover design margin, and
facilitate sodium tetraborate basket
loading and maintenance activities.
Date of publication of individual
notice in the Federal Register: January
25, 2013 (78 FR 5505).
Expiration date of individual notice:
February 25, 2013 (Public comments)
and March 26, 2013 (Hearing requests).
Notice of Issuance of Amendments to
Facility Operating Licenses and
Combined 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 or combined license, as
applicable, proposed no significant
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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
electronically through the Agencywide
Documents Access and Management
System (ADAMS) in the NRC Library at
https://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 pdr.resource@nrc.gov.
TKELLEY on DSK3SPTVN1PROD with NOTICES
Dominion Nuclear Connecticut, Inc.,
Docket No. 50–423, Millstone Power
Station, Unit 3, New London County,
Connecticut
Date of amendment request: April 2,
2012.
Description of amendment request:
The proposed amendment would revise
the Millstone Power Station, Unit 3
Technical Specification surveillance
requirements for snubbers to conform to
the Snubber Examination, Testing, and
Service Life Monitoring Program Plan.
Date of issuance: February 6, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 30 days.
Amendment No.: 257.
Renewed Facility Operating License
No. NPF–49: Amendment revised the
License and Technical Specifications.
Date of initial notice in Federal
Register: May 29, 2012 (77 FR 31657).
The Commission’s related evaluation
of the amendment is contained in a
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Safety Evaluation dated February 6,
2013.
No significant hazards consideration
comments received: No.
Energy Northwest, Docket No. 50–397,
Columbia Generating Station, Benton
County, Washington
Date of application for amendment:
January 9, 2012, as supplemented by
letters dated July 30 and November 14,
2012.
Brief description of amendment: The
amendment implements formatting
changes to the Operating License and
Technical Specifications (TSs) and the
adoption of TSTF–GG–05–01, ‘‘Writers
Guide for Plant-Specific Improved
Technical Specifications,’’ Revision 1.
In addition to these administrative
changes, the amendment implements
editorial changes which do not result in
any changes to the technical or
operating requirements.
Date of issuance: January 29, 2013.
Effective date: As of its date of
issuance and shall be implemented
within 30 days from the date of
issuance.
Amendment No.: 225.
Renewed Facility Operating License
No. NPF–21: The amendment revised
the Facility Operating License and
Technical Specifications.
Date of initial notice in Federal
Register: July 24, 2012 (77 FR 43374).
The supplemental letters dated July 30
and November 14, 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 January 29,
2013.
No significant hazards consideration
comments received: No.
Entergy Nuclear Operations, Inc.,
Docket No. 50–247, Indian Point
Nuclear Generating Unit 2, Westchester
County, New York
Date of application for amendment:
January 11, 2012, and as supplemented
on January 24, 2013.
Brief description of amendment: The
amendment revises Technical
Specification Table 3.3.6–1,
‘‘Containment Purge System and
Pressure Relief Line Isolation
Instrumentation,’’ by changing the
column titled ‘‘ALLOWABLE VALUE’’
to ‘‘TRIP SETPOINT,’’ and replacing the
trip setpoint value of ‘‘≤ 3 ×
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background’’ with a reference to the
Offsite Dose Calculation Manual.
Date of issuance: January 29, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 30 days.
Amendment No.: 272.
Facility Operating License No. DPR–
26: The amendment revised the License
and the Technical Specifications.
Date of initial notice in Federal
Register: May 1, 2012 (77 FR 25758).
The January 24, 2013, supplement
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the NRC
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 January 29,
2013.
No significant hazards consideration
comments received: No.
Entergy Nuclear Operations, Inc.,
Docket No. 50–286, Indian Point
Nuclear Generating Unit 3, Westchester
County, New York
Date of application for amendment:
February 6, 2012, as supplemented on
May 2 and August 6, 2012.
Brief description of amendment: The
amendment approves changes to
Updated Final Safety Analysis Report
(UFSAR) Section 9.13, ‘‘Backup Spent
Fuel Pool Cooling System,’’ to allow use
of the backup spent fuel pool cooling
system when the spent fuel pool cooling
system is out of service.
Date of issuance: January 28, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 30 days. Implementation of the
amendment shall also include revision
of the UFSAR as described in the
licensee’s letter dated February 6, 2012,
as supplemented by letters dated May 2
and August 6, 2012.
Amendment No.: 249.
Facility Operating License Nos. DPR–
26 and DPR–64: The amendment
revised the License and the UFSAR.
Date of initial notice in Federal
Register: August 21, 2012 (77 FR
50537). The supplements dated May 2
and August 6, 2012, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the NRC 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 January 28,
2013.
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No significant hazards consideration
comments received: No.
Entergy Nuclear Vermont Yankee, LLC
and Entergy Nuclear Operations, Inc.,
Docket No. 50–271, Vermont Yankee
Nuclear Power Station, Vernon,
Vermont
Date of amendment request: February
1, 2012, as supplemented by letters
dated August 7 and November 20, 2012.
Brief description of amendment: The
amendment revised Technical
Specification (TS) 4.7.A.6.b.3 for
performing the drywell-to- suppression
chamber leak rate test during an
operating cycle instead of during a
refueling outage.
Date of Issuance: January 30, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 60 days.
Amendment No.: 254.
Facility Operating License No. DPR–
28: The amendment revised the
Renewed Facility Operating License and
the Technical Specifications.
Date of initial notice in Federal
Register: April 3, 2012 (77 FR 20074).
The supplemental letters dated August
7 and November 20, 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 this amendment is contained in a
Safety Evaluation dated January 30,
2013.
No significant hazards consideration
comments received: No.
TKELLEY on DSK3SPTVN1PROD with NOTICES
Entergy Nuclear Vermont Yankee, LLC
and Entergy Nuclear Operations, Inc.,
Docket No. 50–271, Vermont Yankee
Nuclear Power Station, Vernon,
Vermont
Date of amendment request: February
1, 2012, as supplemented by letter dated
May 8, 2012.
Brief description of amendment: The
amendment revised Technical
Specification 3.3.B.3 for bypassing the
Rod Worth Minimizer consistent with
the allowances and required actions
recommended in the Standard
Technical Specifications, NUREG–1433,
Revision 3.
Date of Issuance: January 30, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 60 days.
Amendment No.: 255.
Facility Operating License No. DPR–
28: The amendment revised the License
and the Technical Specifications.
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Date of initial notice in Federal
Register: April 17, 2012 (77 FR 22812).
The supplemental letter dated May 8,
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.
The Commission’s related evaluation
of this amendment is contained in a
Safety Evaluation dated January 30,
2013.
No significant hazards consideration
comments received: No.
NextEra Energy Point Beach, LLC,
Docket Nos. 50–266 and 50–301, Point
Beach Nuclear Plant, Units 1 and 2,
Town of Two Creeks, Manitowoc
County, Wisconsin
Date of application for amendments:
August 16, 2012.
Brief description of amendments: The
amendments revise Technical
Specification 5.3, ‘‘Facility Staff
Qualifications,’’ to clarify the required
qualifications of the Operations
Manager.
Date of issuance: January 29, 2013.
Effective date: As of the date of
issuance and shall be implemented with
30 days from the date of issuance.
Amendment Nos.: 248 (Unit 1) and
252 (Unit 2).
Renewed Facility Operating License
Nos. DPR–24 and DPR–27: Amendments
revise the Renewed Facility Operating
License and Technical Specifications.
Date of initial notice in Federal
Register: October 30, 2012 (77 FR
65725).
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated January 29,
2013.
No significant hazards consideration
comments received: No
NextEra Energy Seabrook, LLC, Docket
No. 50–443, Seabrook Station, Unit No.
1, Rockingham County, New Hampshire
Date of amendment request: April 30,
2012.
Description of amendment request:
The amendment made changes to the
Seabrook Emergency Plan associated
with the initiating conditions involving
a loss of safety system annunciation or
indication in the control room. The
amendment revises the emergency
action levels (EALs) to include radiation
monitoring indications within the
aggregate of safety system indications
that are considered when evaluating a
loss of safety system indications rather
than separate EALs.
Date of issuance: January 31, 2013.
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11695
Effective date: As of its date of
issuance and shall be implemented
within 90 days.
Amendment No.: 133.
Facility Operating License No. NPF–
86: The amendment revised the License.
Date of initial notice in Federal
Register: May 29, 2012 (77 FR 31661).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated January 31,
2013.
No significant hazards consideration
comments received: No.
Northern States Power Company—
Minnesota (NSPM), Docket No. 50–263,
Monticello Nuclear Generating Plant
(MNGP), Wright County, Minnesota
Date of application for amendment:
May 8, 2012.
Brief description of amendment: The
amendment revises the Technical
Specification, Section 3.3.1.1, ‘‘Reactor
Protection System (RPS)
Instrumentation,’’ requirements
pertaining to the Average Power Range
Monitors (APRMs). Specifically, it
allows a time period for restoration
before declaring the channels inoperable
when the absolute difference between
the APRM channel power and
calculated thermal power exceeds the
limit of Technical Specification
Surveillance Requirement 3.3.1.2.
Date of issuance: January 25, 2013.
Effective date: This license
amendment is effective as of the date of
its issuance, and shall be implemented
within 90 days of issuance.
Amendment No.: 171.
Facility Operating License No. DPR–
22. Amendment revises the Renewed
Facility Operating License and
Technical Specifications.
Date of initial notice in Federal
Register: July 24, 2012 (77 FR 43378).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated January 25,
2013.
No significant hazards consideration
comments received: No.
Northern States Power Company—
Minnesota, Docket Nos. 50–282 and 50–
306, Prairie Island Nuclear Generating
Plant, Units 1 and 2, Goodhue County,
Minnesota
Date of application for amendments:
October 27, 2009, as supplemented by
letters dated April 29, May 25, June 23,
August 12, and December 17 of 2010;
June 22, July 11, August 9, and
December 8 of 2011; February 13,
February 24, and September 13 of 2012.
Brief description of amendments:
These amendments modify the Prairie
Island Nuclear Generating Plant, Units 1
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and 2, Technical Specifications (TSs)
and licensing basis that supports a full
scope implementation of the Alternative
Source Term Methodology. The
amendments also incorporate TS Task
Force-490, ‘‘Deletion of E-Bar Definition
and Revision to RCS [Reactor Coolant
System] Specific Activity Tech Spec,’’
Revision 0.
Date of issuance: January 22, 2013.
Effective date: As of the date of
issuance. The license conditions shall
be implemented within 30 days. The
balance of the license amendment shall
be implemented in accordance with the
terms of the license conditions.
Amendment Nos.: 206, 193.
Renewed Facility Operating License
Nos. DPR–42 and DPR–60: Amendments
revised the Facility Operating Licenses,
Appendix B, and the Technical
Specifications.
Date of initial notice in Federal
Register: April 6, 2010 (75 FR 17466).
The supplemental letters contained
clarifying information and did not
change the initial no significant hazards
consideration determination, and did
not expand the scope of the original
Federal Register notice.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated January 22,
2013.
No significant hazards consideration
comments received: No.
Pacific Gas and Electric Company,
Docket Nos. 50–275 and 50–323, Diablo
Canyon Nuclear Power Plant, Units 1
and 2, San Luis Obispo County,
California
Date of application for amendment:
June 1, 2011, as supplemented by letters
dated February 6, May 31, August 6, and
November 1, 2012.
Brief description of amendment: The
amendments revised Technical
Specifications (TS) 3.7.5, ‘‘Auxiliary
Feedwater (AFW) System,’’ 3.6.6,
‘‘Containment Spray and Cooling
Systems,’’ 3.8.1, ‘‘AC Sources—
Operating,’’ 3.8.9, ‘‘Distribution
Systems—Operating,’’ and Example 1.3–
3 to clarify the operability of an AFW
train during alternate alignments;
establish conditions, required actions,
and completion times when one steam
supply to the turbine driven AFW pump
is inoperable concurrent with an
inoperable motor driven AFW train; and
remove second completion times from
TSs. These changes are consistent with
the guidance provided in Technical
Specifications Task Force (TSTF)
Travelers TSTF–245, Revision 1, ‘‘AFW
Train Operable when in Service,’’
TSTF–340, Revision 3, ‘‘Allow 7 day
completion Time for a Turbine-driven
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AFW Pump Inoperable,’’ TSTF–412,
Revision 3, ‘‘Provide Actions for One
Steam Supply to Turbine Driven AFW/
EFW Pump Inoperable,’’ and TSTF–439,
Revision 2, ‘‘Eliminate Second
Completion Times Limiting Time From
Discovery of Failure to Meet an LCO.’’
Date of issuance: January 31, 2013.
Effective date: As of its date of
issuance and shall be implemented
within 90 days from the date of
issuance.
Amendment Nos.: Unit 1–215; Unit
2–217.
Facility Operating License Nos. DPR–
80 and DPR–82: The amendments
revised the Facility Operating Licenses
and Technical Specifications.
Date of initial notice in Federal
Register: December 31, 2011 (76 FR
77569). The supplemental letters dated
February 6, May 31, August 6, and
November 1, 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.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated January 31,
2013.
No significant hazards consideration
comments received: No.
November 6, 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.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated January 28,
2013.
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 30, December 13, 2012.
Brief description of amendment: The
amendments revised the North Anna
Technical Specifications (TSs) regarding
steam generator tube inspections and
reporting as described in TSTF–510,
Revision 2, ‘‘Revision to Steam
Generator Program Inspection
Frequencies and Tube Sample
Selection.’’ The changes are consistent
with NRC-approved Industry TSTF
Standard Technical Specifications
change TSTF–510, Revision 2.
Date of issuance: January 28, 2013.
Virginia Electric and Power Company, et
Effective date: As of the date of
al., Docket Nos. 50–280 and 50–281,
issuance and shall be implemented
Surry Power Station, Units 1 and 2,
within 60 days from the date of
Surry County, Virginia
issuance.
Date of application for amendments:
Amendment Nos.: Unit 1–269 and
July 28, 2012.
Unit 2–250.
Brief Description of amendments:
These amendments revise Limiting
Renewed Facility Operating License
Condition for Operation (LCO) 3.1.H,
Nos. NPF–4 and NPF–7: Amendments
‘‘Steam Generator (SG) Tube Integrity,’’
changed the licenses and the technical
Specification 6.4.Q, ‘‘Steam Generator
specifications.
(SG) Program,’’ and Specification
Date of initial notice in Federal
6.6.A.3, ‘‘Steam Generator Tube
Register: October 2, 2012 (77 FR
Inspection Report,’’ and include
60155). The supplement dated
technical specification (TS) Bases
December 13, 2012, provided additional
changes that summarize and clarify the
information that clarified the
purpose of the TS in accordance with
application, did not expand the scope of
TS Task Force Traveler (TSTF) 510,
the application as originally noticed,
‘‘Revision to Steam Generator Program
and did not change the staff’s original
Inspection Frequencies and Tube
Sample Selection.’’
proposed no significant hazards
Date of issuance: January 28, 2013.
consideration determination.
Effective date: As of the date of
The Commission’s related evaluation
issuance and shall be implemented
of the amendments is contained in a
within 60 days.
Safety Evaluation dated January 28,
Amendment Nos.: 278, 278.
2013.
Renewed Facility Operating License
Nos. DPR–32 and DPR–37: Amendments
No significant hazards consideration
change the licenses and the technical
comments received: No.
specifications.
Date of initial notice in Federal
Register: October 16, 2012 (77 FR
63351). The supplements dated
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Notice of Issuance of Amendments to
Facility Operating Licenses and
Combined Licenses and Final
Determination of No Significant
Hazards Consideration and
Opportunity for a Hearing (Exigent
Public Announcement or Emergency
Circumstances)
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 for the
amendment 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.
Because of exigent or emergency
circumstances associated with the date
the amendment was needed, there was
not time for the Commission to publish,
for public comment before issuance, its
usual notice of consideration of
issuance of amendment, proposed no
significant hazards consideration
determination, and opportunity for a
hearing.
For exigent circumstances, the
Commission has either issued a Federal
Register notice providing opportunity
for public comment or has used local
media to provide notice to the public in
the area surrounding a licensee’s facility
of the licensee’s application and of the
Commission’s proposed determination
of no significant hazards consideration.
The Commission has provided a
reasonable opportunity for the public to
comment, using its best efforts to make
available to the public means of
communication for the public to
respond quickly, and in the case of
telephone comments, the comments
have been recorded or transcribed as
appropriate and the licensee has been
informed of the public comments.
In circumstances where failure to act
in a timely way would have resulted, for
example, in derating or shutdown of a
nuclear power plant or in prevention of
either resumption of operation or of
increase in power output up to the
plant’s licensed power level, the
Commission may not have had an
opportunity to provide for public
comment on its no significant hazards
consideration determination. In such
case, the license amendment has been
issued without opportunity for
comment. If there has been some time
for public comment but less than 30
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days, the Commission may provide an
opportunity for public comment. If
comments have been requested, it is so
stated. In either event, the State has
been consulted by telephone whenever
possible.
Under its regulations, the Commission
may issue and make an amendment
immediately effective, notwithstanding
the pendency before it of a request for
a hearing from any person, in advance
of the holding and completion of any
required hearing, where it has
determined that no significant hazards
consideration is involved.
The Commission has applied the
standards of 10 CFR 50.92 and has made
a final determination that the
amendment involves no significant
hazards consideration. The basis for this
determination is contained in the
documents related to this action.
Accordingly, the amendments have
been issued and made effective 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 51.12(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 application for
amendment, (2) the amendment to
Facility Operating License or Combined
License, as applicable, 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
electronically through the Agencywide
Documents Access and Management
System (ADAMS) in the NRC Library at
https://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 pdr.resource@nrc.gov.
The Commission is also offering an
opportunity for a hearing with respect to
the issuance of the amendment. Within
60 days after the date of publication of
this notice, any person(s) whose interest
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11697
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 or combined license.
Requests for a hearing and a petition for
leave to intervene shall be filed in
accordance with the Commission’s
‘‘Agency Rules of Practice and
Procedures’’ 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, and electronically on
the Internet at the NRC’s Web site,
https://www.nrc.gov/reading-rm/doccollections/cfr/. If there are problems in
accessing the document, contact the
PDR’s Reference staff at 1–800–397–
4209, 301–415–4737, or by email to
pdr.resource@nrc.gov. 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 petitioner intends to
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rely in proving the contention at the
hearing. The petitioner must also
provide references to those specific
sources and documents of which the
petitioner is aware and on which the
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 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 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. Since the Commission has
made a final determination that the
amendment involves no significant
hazards consideration, if a hearing is
requested, it will not stay the
effectiveness of the amendment. Any
hearing held would take place while the
amendment is in effect.
All documents filed in the 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 EFiling 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
hearing.docket@nrc.gov, 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
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hearing (even in instances in which the
participant, or its counsel or
representative, already holds an NRCissued 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
NRC’s public Web site at https://
www.nrc.gov/site-help/e-submittals/
apply-certificates.html. System
requirements for accessing the ESubmittal server are detailed in NRC’s
‘‘Guidance for Electronic Submission,’’
which is available on the agency’s
public Web site at https://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 Webbased submission form, including the
installation of the Web browser plug-in,
is available on the NRC’s public Web
site at https://www.nrc.gov/site-help/esubmittals.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
guidance available on the NRC’s public
Web site at https://www.nrc.gov/sitehelp/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 EFiling 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
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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 https://
www.nrc.gov/site-help/esubmittals.html, by email at
MSHD.Resource@nrc.gov, or by a tollfree 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 firstclass 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 https://
ehd1.nrc.gov/ehd/, unless excluded
pursuant to an order of the Commission,
or the presiding officer. Participants are
requested not to include personal
privacy information, such as social
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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.
Calvert Cliffs Nuclear Power Plant, LLC,
Docket No. 50–318, Calvert Cliffs
Nuclear Power Plant, Unit 2, Calvert
County, Maryland
TKELLEY on DSK3SPTVN1PROD with NOTICES
Date of amendment request: January
22, 2013, as supplemented by letter
dated January 24, 2013.
Description of amendment request:
The amendment revised Appendix C of
the Renewed Facility Operating License
by adding a license condition for
Technical Specification 3.6.6, which
will allow the ‘‘B’’ train of the
Containment Cooling System to be
considered operable with a single
containment cooling fan and cooler by
limiting the refueling water storage tank
water temperature, containment average
air temperature, containment air
pressure, and saltwater inlet
temperature for the period from January
26, to February 17, 2013.
Date of issuance: January 25, 2013.
Effective date: As of the date of
issuance, and shall be implemented
within 30 days.
Amendment No.: 280.
Renewed Facility Operating License
No. DPR–69: Amendment revised the
License and Appendix C.
Public comments requested as to
proposed no significant hazards
consideration (NSHC): No. The
Commission’s related evaluation of the
amendment, finding of emergency
circumstances, state consultation, and
final NSHC determination are contained
in a safety evaluation dated January 25,
2013.
Attorney for licensee: Steven L.
Miller, General Counsel, Constellation
Energy Nuclear Group, LLC, 100
Constellation Way, Suite 200c,
Baltimore, MD 21202.
NRC Branch Chief: George Wilson.
Dated at Rockville, Maryland, this 8th day
of February 2013.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2013–03582 Filed 2–15–13; 8:45 am]
BILLING CODE 7590–01–P
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NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0001]
Sunshine Act Meeting Notice
AGENCY HOLDING THE MEETINGS: Nuclear
Regulatory Commission.
DATE: Weeks of February 18, 25, March
4, 11, 18, 25, 2013.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
Week of February 18, 2013
Wednesday, February 20, 2013
12:55 p.m. Affirmation Session (Public
Meeting) (Tentative)
NextEra Energy Seabrook, LLC
(Seabrook Station), New England
Coalition and Friends of the Coast’s
Notice, and Supporting Brief, of
Appeal of ASLBP No. 10–906–02–
LR–BD01 to NextEra Energy
Seabrook, LLC (Nov. 19, 2012)
(Tentative).
This meeting will be webcast live at
the Web address—www.nrc.gov.
1:00 p.m. Briefing on Uranium
Recovery (Public Meeting) (Contact:
Bill von Till, 301–415–0598).
This meeting will be webcast live at
the Web address—www.nrc.gov.
11699
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
*
*
*
*
*
The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify
Kimberly Meyer, NRC Disability
Program Manager, at 301–287–0727, or
by email at kimberly.meyerchambers@nrc.gov. Determinations on
requests for reasonable accommodation
will be made on a case-by-case basis.
*
*
*
*
*
This notice is distributed
electronically to subscribers. If you no
longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301–415–1969),
or send an email to
darlene.wright@nrc.gov.
Dated: February 13, 2013.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2013–03845 Filed 2–14–13; 4:15 pm]
BILLING CODE 7590–01–P
Thursday, February 21, 2013
9:30 a.m. Briefing on the Threat
Environment Assessment (Closed—
Ex. 1).
Week of February 25, 2013—Tentative
There are no meetings scheduled for
the week of February 25, 2013.
Week of March 4, 2013—Tentative
There are no meetings scheduled for
the week of March 4, 2013.
Week of March 11, 2013—Tentative
There are no meetings scheduled for
the week of March 11, 2013.
Week of March 18, 2013—Tentative
There are no meetings scheduled for
the week of March 18, 2013.
Week of March 25, 2013—Tentative
There are no meetings scheduled for
the week of March 25, 2013.
*
*
*
*
*
* The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—301–415–1292.
Contact person for more information:
Rochelle Bavol, 301–415–1651.
*
*
*
*
*
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POSTAL REGULATORY COMMISSION
[Docket No. CP2013–50; Order No. 1655]
International Mail Contract
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
The Commission is noticing a
recent Postal Service filing concerning a
successor International Reply Service
Competitive Contract 3 Negotiated
Service Agreement. This notice informs
the public of the filing, invites public
comment, and takes other
administrative steps.
DATES: Comments are due: February 20,
2013.
ADDRESSES: Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Those who cannot submit
comments electronically should contact
the person identified in the FOR FURTHER
INFORMATION CONTACT section by
telephone for advice on filing
alternatives.
FOR FURTHER INFORMATION CONTACT:
Stephen L. Sharfman, General Counsel,
at 202–789–6820.
SUPPLEMENTARY INFORMATION:
SUMMARY:
E:\FR\FM\19FEN1.SGM
19FEN1
]]>Agencies
[Federal Register Volume 78, Number 33 (Tuesday, February 19, 2013)]
[Notices]
[Pages 11688-11699]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-03582]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0032]
Biweekly Notice, Applications and Amendments to Facility
Operating Licenses and Combined 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 (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 or combined
license, as applicable, 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 January 24, 2013, to February 6, 2013. The
last biweekly notice was published on February 5, 2013 (78 FR 8195).
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and are publically available,
by searching on https://www.regulations.gov under Docket ID NRC-2013-
0032. You may submit comments by any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2013-0032. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
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.
[[Page 11689]]
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:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2013-0032 when contacting the NRC
about the availability of information regarding this document. You may
access information related to this document by any of the following
methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2013-0032.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at https://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 pdr.resource@nrc.gov. 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-2013-0032 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 that that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at https://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely 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 that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely 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 and Combined 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 Section 50.92 of Title 10 of the Code
of Federal Regulations (10 CFR), 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; or (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 or
combined license. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ``Agency
Rules of Practice and Procedures'' 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 regulations are accessible electronically from the NRC Library on
the NRC's Web site at https://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
[[Page 11690]]
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
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 the 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 hearing.docket@nrc.gov, 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 https://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 https://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 https://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 https://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 Web site
at https://www.nrc.gov/site-help/e-submittals.html, by email at
MSHD.Resource@nrc.gov, 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
[[Page 11691]]
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
https://ehd1.nrc.gov/ehd/, unless excluded 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. Requests for hearing,
petitions for leave to intervene, and motions for leave to file new or
amended contentions that are filed after the 60-day deadline will not
be entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the following three
factors in 10 CFR 2.309(c)(1): (i) The information upon which the
filing is based was not previously available; (ii) the information upon
which the filing is based is materially different from information
previously available; and (iii) the filing has been submitted in a
timely fashion based on the availability of the subsequent information.
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 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's PDR Reference staff at 1-800-397-4209,
301-415-4737, or by email to pdr.resource@nrc.gov.
Carolina Power and Light Company, et al., Docket No. 50-400, Shearon
Harris Nuclear Power Plant, Unit 1, Wake County, North Carolina
Date of amendment request: November 29, 2012, as supplemented by
letter dated January 3, 2013.
Description of amendment request: The amendment revised the
Technical Specification (TS) surveillance requirements for addressing a
missed surveillance, and is consistent with the U.S. Nuclear Regulatory
Commission approved Revision 6 of Technical Specification Task Force
(TSTF) Standard TSs Change Traveler TSTF-358, ``Missed Surveillance
Requirements.''
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 change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change revises the Technical Specifications (TS)
Table 3.3-4, Functional Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage--Secondary time delay values.
The Loss of Offsite Power, 6.9 kV (kilovolt) Emergency Bus
Undervoltage--Secondary instrumentation functions are not initiators
to any accident previously evaluated. As such, the probability of an
accident previously evaluated is not increased. The revised values
continue to provide reasonable assurance that the Loss of Offsite
Power, 6.9 kV (kilovolt) Emergency Bus Undervoltage--Secondary
function will continue to perform its intended safety functions. As
a result, the proposed change will not increase the consequences of
an accident previously evaluated.
Concurrent with this proposed change, the Harris Nuclear Plant
is revising its large break loss of coolant accident analysis. The
revised analysis will be evaluated in accordance with 10 CFR 50.59
to confirm that a change to the technical specifications
incorporated in the license is not required, and the change does not
meet any of the criteria in Paragraph (c)(2) of that regulation. The
revised analysis will employ the plant-specific methodology ANP-
3011(P), Harris Nuclear Plant, Unit 1, Realistic Large Break LOCA
Analysis, Revision 1, as approved by NRC Safety Evaluation dated May
30, 2012.
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 change revises the Technical Specification (TS)
Table 3.3-4, Functional Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage--Secondary time delay values.
No new operational conditions beyond those currently allowed are
introduced. This change is consistent with the safety analyses
assumptions and current plant operating practices. This simply
corrects the setpoint consistent with the accident analyses and
therefore cannot create the possibility of a new or different kind
of accident from any previously evaluated accident.
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 change involve a significant reduction in
the margin of safety?
Response: No.
The proposed change revises the Technical Specifications (TS)
Table 3.3-4, Functional Unit 9.b. Loss of Offsite Power, 6.9 kV
(kilovolt) Emergency Bus Undervoltage--Secondary time delay values.
This proposed change implements a reduced time delay to isolate
safety buses from offsite power if a Loss of Coolant Accident were
to occur coincident with a sustained degraded voltage condition.
This provides improved margin to ensure that emergency core cooling
system pumps inject water into the reactor vessel within the time
assumed and evaluated in the accident analysis.
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.
Attorney for licensee: David T. Conley, Manager--Senior Counsel--
Legal Department, Progress Energy Service Company, LLC, Post Office Box
1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Jessie F. Quichocho.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287,
Oconee Nuclear Station, Units 1, 2, and 3 (ONS1, ONS2, and ONS3),
Oconee County, South Carolina
Date of amendment request: October 30, 2012.
Description of amendment request: The proposed amendment would
revise the Technical Specifications (TSs) to specify that TS 3.8.1
Required Action (RA) C.2.2.5 is cumulative over a 3-year time period
for each Keowee Hydroelectric Unit (KHU). The two KHUs serve as the
emergency power supply for ONS1, ONS2, and ONS3. RA C.2.2.5 currently
allows a 45-day Completion Time once every 3 years to
[[Page 11692]]
restore an inoperable KHU to service. This revision would allow the 45-
day Completion Time to be used as a cumulative allowance over 3 years,
rather than once every 3 years. This Completion Time is used for major
Keowee Hydroelectric Unit (KHU) maintenance.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee provided
its analysis of the issue of no significant hazards consideration,
which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment adds a note to the 45-day Completion Time
for Technical Specification (TS) 3.8.1 Required Action (RA) C.2.2.5
to clarify the 45 days is cumulative for each Keowee Hydroelectric
Unit (KHU) over a rolling 3-year time period rather than limited to
one continuous 45-day time period. During the time that one KHU is
inoperable for > 72 hours, a Lee Combustion Turbine (LCT) will be
energizing both standby buses, two offsite power sources will be
maintained available, and maintenance on electrical distribution
systems will not be performed unless necessary.
There is no adverse impact on containment integrity,
radiological release pathways, fuel design, filtration systems, main
steam relief valve set points, or radwaste systems. No new
radiological release pathways are created.
The consequences of an event occurring during the modified 45-
day Completion Time, which clarifies the 45 days is cumulative for
each KHU over a rolling 3-year time period, are the same as those
that would occur during a continuous 45-day Completion Time. Duke
Energy reviewed the Probabilistic Risk Assessment (PRA) to gain
additional insights concerning the configuration of ONS with one KHU
inoperable for one continuous 45 day period versus multiple time
periods totally [totaling] 45-days. Based on this review, Duke
Energy concluded that there is no change in risk.
Therefore, the probability or consequences of an accident
previously evaluated is not significantly increased.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment adds a note to the 45-day Completion Time
for TS 3.8.1 Required Action C.2.2.5 to clarify the 45 days is
cumulative for each KHU over a rolling 3-year time period rather
than limited to one continuous 45-day time period. During the time
period that one KHU is inoperable and the 45-day Completion Time is
being applied, the redundancy requirement for the emergency power
source will be fulfilled by an LCT [Lee Combustion Turbine] and
other compensatory measures required by TS 3.8.1 RA C.2.2.1,
C.2.2.2, C.2.2.3, and C.2.2.4 will be in place to minimize
electrical power system vulnerabilities.
The proposed change to the 45-day Completion Time does not
involve a physical effect on the Oconee Units, nor is there any
increased risk of an Oconee Unit trip or reactivity excursion. No
new failure modes or credible accident scenarios are postulated from
this activity.
Therefore, the possibility of a new or different kind of
accident from any kind of accident previously evaluated is not
created.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed amendment adds a note to the 45-day Completion Time
for TS 3.8.1 RA C.2.2.5 to clarify the 45 days is cumulative for
each KHU over a rolling 3-year time period rather than limited to
one continuous 45-day time period. During the time period that one
KHU is inoperable and the 45-day Completion Time is being applied,
the redundancy requirement for the emergency power source will be
fulfilled by an LCT and other compensatory measures required by TS
3.8.1 RA C.2.2.1, C.2.2.2, C.2.2.3, and C.2.2.4 will be in place to
minimize electrical power system vulnerabilities.
The proposed TS change does not involve: 1) a physical
alteration of the Oconee Units; 2) the installation of new or
different equipment; 3) operating any installed equipment in a new
or different manner; 4) a change to any set points for parameters
which initiate protective or mitigation action; or 5) any impact on
the fission product barriers or safety limits.
Therefore, this request 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.
Attorney for licensee: Lara S. Nichols, Associate General Counsel,
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC
28202-1802.
NRC Branch Chief: Robert J. Pascarelli.
Florida Power and Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Nuclear Generating Units 3 and 4, Miami-Dade County, Florida
Date of amendment request: October 30, 2012.
Description of amendment request: The proposed amendments would
decrease the time limits in certain actions and surveillance
requirements of Technical Specification (TS) 3.5.2, ``ECCS [emergency
core cooling system] Subsystems,'' and revise certain footnotes of TS
3.5.2 for clarity.
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?
No. The proposed amendment does not change or modify the design
or operation of ECCS systems, subsystems, or components. The
proposed amendment does not affect any precursors to any accident
previously evaluated or do not adversely affect known mitigation
equipment or strategies. The proposed amendment provides better
assurance that the ECCS systems, subsystems, and components are
properly aligned to support safe reactor operation consistent with
the licensing and design basis requirements. The proposed changes
addressing cascading of emergency power requirements are considered
non-intent changes. Therefore, the proposed amendment 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?
No. The proposed amendment provides better assurance that the
ECCS systems, subsystems, and components are properly aligned to
support safe reactor operation consistent with the licensing and
design basis requirements. No new accident initiators are introduced
directly or indirectly by the proposed changes. The changes
addressing cascading of emergency power requirements are considered
non-intent changes. Therefore, the proposed amendment 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 the margin of safety?
No. The proposed amendment provides better assurance that the
ECCS systems, subsystems, and components are properly aligned to
support safe reactor operation consistent with the licensing and
design basis requirements. The proposed changes correct deficiencies
regarding TS LCO [limiting condition for operation] 3.5.2.d and TS
SR [surveillance requirement] 4.5.2.a to assure ECCS availability is
maintained within the assumptions of the safety analysis. Therefore,
the proposed amendment does not involve a significant reduction in
the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: James Petro, Managing Attorney--Nuclear,
Florida
[[Page 11693]]
Power & Light, P.O. Box 14000, Juno Beach, Florida 33408-0420.
NRC Branch Chief: Jessie F. Quichocho.
Southern Nuclear Operating Company Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Burke County,
Georgia
Date of amendment request: December 7, 2012, and revised on January
25, 2013.
Description of amendment request: The proposed change would amend
Combined License Nos. NPF-91 and NPF-92 for Vogtle Electric Generating
Plant (VEGP) Units 3 and 4 in regard to the Primary Sampling System
(PSS) by: (1) replacing containment air return check valve PSS-PL-V024
with a solenoid-operated valve, and (2) redesigning the PSS inside-
containment header and adding a PSS containment penetration.
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 Primary Sampling System (PSS) provides the safety-related
function of preserving containment integrity by isolation of the PSS
lines penetrating containment. The proposed amendment will enhance
the ability of the PSS to perform its nonsafety-related function of
providing the capability to obtain reactor coolant and containment
atmosphere samples, while maintaining the ability of the PSS to
perform its safety-related containment isolation function. The
replacement of a check valve with a solenoid-operated containment
isolation valve and the redesigned inside-containment header does
not affect the safety-related function of isolating the PSS lines
for containment isolation. The components added by this proposed
activity, including tubing and the solenoid-operated containment
isolation valve, are designed to the same codes and standards as
other components addressed in the certified design that perform
similar functions. The additional PSS containment penetration is a
passive extension of containment and is identical in form, fit, and
function to other PSS sampling containment penetrations currently
addressed in the certified AP1000 plant design. The addition of a
new PSS containment penetration will not change the maximum
allowable leakage rate allowed by Technical Specifications and
verified periodically in accordance with regulations. Furthermore,
the proposed PSS configuration changes will neither impact any
accident source term parameter or fission product barrier nor affect
radiological dose consequence analysis.
Therefore, the proposed amendment 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 additional containment penetration is similar in form, fit,
and function to the PSS penetrations that are currently described in
the Updated Final Safety Analysis Report. Because the PSS changes
use valve types, piping, and a containment penetration consistent
with those already described in the Updated Final Safety Analysis
Report, no new failure modes or equipment failure initiators are
introduced by these changes. Accordingly, the proposed changes do
not create any new malfunctions, failure mechanisms, or accident
initiators.
Therefore, the proposed amendment 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 containment isolation function is not changed by this
activity and is bounded by the existing design. The proposed PSS
containment penetration is similar in form, fit, and function to
other containment penetrations in similar applications in the
current certified AP1000 plant design. The additional PSS
containment penetration is an extension of containment, and,
therefore, does not affect containment or its ability to perform its
design function. The addition of PSS components, including the
solenoid-operated containment isolation valve, the additional PSS
containment penetration, and the associated tubing, do not exceed or
alter a design basis or safety limit. Because the containment
isolation function, containment leakage rate limit, potential
containment leakage, and protective shielding are not changed by
this activity and are bounded by the existing design, there is no
change to any current margin of safety.
Therefore, the proposed amendment 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.
Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham
LLP, 1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Acting Branch Chief: Lawrence Burkhart.
Previously Published Notices of Consideration of Issuance of Amendments
to Facility Operating Licenses and Combined Licenses, Proposed No
Significant Hazards Consideration Determination, and Opportunity for a
Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Florida Power and Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Generating Units 3 and 4, Miami-Dade County, Florida
Date of application for amendments: September 6, 2012.
Description of amendments request: The proposed amendments would
reduce the minimum sodium tetraborate basket loading to 7500 pounds
mass in order to lessen the long term sump pH profile, recover design
margin, and facilitate sodium tetraborate basket loading and
maintenance activities.
Date of publication of individual notice in the Federal Register:
January 25, 2013 (78 FR 5505).
Expiration date of individual notice: February 25, 2013 (Public
comments) and March 26, 2013 (Hearing requests).
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined 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 or combined license, as applicable, proposed no
significant
[[Page 11694]]
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 electronically through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at https://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
pdr.resource@nrc.gov.
Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power
Station, Unit 3, New London County, Connecticut
Date of amendment request: April 2, 2012.
Description of amendment request: The proposed amendment would
revise the Millstone Power Station, Unit 3 Technical Specification
surveillance requirements for snubbers to conform to the Snubber
Examination, Testing, and Service Life Monitoring Program Plan.
Date of issuance: February 6, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 30 days.
Amendment No.: 257.
Renewed Facility Operating License No. NPF-49: Amendment revised
the License and Technical Specifications.
Date of initial notice in Federal Register: May 29, 2012 (77 FR
31657).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated February 6, 2013.
No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of application for amendment: January 9, 2012, as supplemented
by letters dated July 30 and November 14, 2012.
Brief description of amendment: The amendment implements formatting
changes to the Operating License and Technical Specifications (TSs) and
the adoption of TSTF-GG-05-01, ``Writers Guide for Plant-Specific
Improved Technical Specifications,'' Revision 1. In addition to these
administrative changes, the amendment implements editorial changes
which do not result in any changes to the technical or operating
requirements.
Date of issuance: January 29, 2013.
Effective date: As of its date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment No.: 225.
Renewed Facility Operating License No. NPF-21: The amendment
revised the Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: July 24, 2012 (77 FR
43374). The supplemental letters dated July 30 and November 14, 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 January 29, 2013.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-247, Indian Point
Nuclear Generating Unit 2, Westchester County, New York
Date of application for amendment: January 11, 2012, and as
supplemented on January 24, 2013.
Brief description of amendment: The amendment revises Technical
Specification Table 3.3.6-1, ``Containment Purge System and Pressure
Relief Line Isolation Instrumentation,'' by changing the column titled
``ALLOWABLE VALUE'' to ``TRIP SETPOINT,'' and replacing the trip
setpoint value of ``<= 3 x background'' with a reference to the Offsite
Dose Calculation Manual.
Date of issuance: January 29, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 30 days.
Amendment No.: 272.
Facility Operating License No. DPR-26: The amendment revised the
License and the Technical Specifications.
Date of initial notice in Federal Register: May 1, 2012 (77 FR
25758). The January 24, 2013, supplement provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the NRC
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 January 29, 2013.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point
Nuclear Generating Unit 3, Westchester County, New York
Date of application for amendment: February 6, 2012, as
supplemented on May 2 and August 6, 2012.
Brief description of amendment: The amendment approves changes to
Updated Final Safety Analysis Report (UFSAR) Section 9.13, ``Backup
Spent Fuel Pool Cooling System,'' to allow use of the backup spent fuel
pool cooling system when the spent fuel pool cooling system is out of
service.
Date of issuance: January 28, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 30 days. Implementation of the amendment shall also
include revision of the UFSAR as described in the licensee's letter
dated February 6, 2012, as supplemented by letters dated May 2 and
August 6, 2012.
Amendment No.: 249.
Facility Operating License Nos. DPR-26 and DPR-64: The amendment
revised the License and the UFSAR.
Date of initial notice in Federal Register: August 21, 2012 (77 FR
50537). The supplements dated May 2 and August 6, 2012, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC 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 January 28, 2013.
[[Page 11695]]
No significant hazards consideration comments received: No.
Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations,
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon,
Vermont
Date of amendment request: February 1, 2012, as supplemented by
letters dated August 7 and November 20, 2012.
Brief description of amendment: The amendment revised Technical
Specification (TS) 4.7.A.6.b.3 for performing the drywell-to-
suppression chamber leak rate test during an operating cycle instead of
during a refueling outage.
Date of Issuance: January 30, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 60 days.
Amendment No.: 254.
Facility Operating License No. DPR-28: The amendment revised the
Renewed Facility Operating License and the Technical Specifications.
Date of initial notice in Federal Register: April 3, 2012 (77 FR
20074). The supplemental letters dated August 7 and November 20, 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 this amendment is contained
in a Safety Evaluation dated January 30, 2013.
No significant hazards consideration comments received: No.
Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations,
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon,
Vermont
Date of amendment request: February 1, 2012, as supplemented by
letter dated May 8, 2012.
Brief description of amendment: The amendment revised Technical
Specification 3.3.B.3 for bypassing the Rod Worth Minimizer consistent
with the allowances and required actions recommended in the Standard
Technical Specifications, NUREG-1433, Revision 3.
Date of Issuance: January 30, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 60 days.
Amendment No.: 255.
Facility Operating License No. DPR-28: The amendment revised the
License and the Technical Specifications.
Date of initial notice in Federal Register: April 17, 2012 (77 FR
22812). The supplemental letter dated May 8, 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.
The Commission's related evaluation of this amendment is contained
in a Safety Evaluation dated January 30, 2013.
No significant hazards consideration comments received: No.
NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc
County, Wisconsin
Date of application for amendments: August 16, 2012.
Brief description of amendments: The amendments revise Technical
Specification 5.3, ``Facility Staff Qualifications,'' to clarify the
required qualifications of the Operations Manager.
Date of issuance: January 29, 2013.
Effective date: As of the date of issuance and shall be implemented
with 30 days from the date of issuance.
Amendment Nos.: 248 (Unit 1) and 252 (Unit 2).
Renewed Facility Operating License Nos. DPR-24 and DPR-27:
Amendments revise the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: October 30, 2012 (77 FR
65725).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 29, 2013.
No significant hazards consideration comments received: No
NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit
No. 1, Rockingham County, New Hampshire
Date of amendment request: April 30, 2012.
Description of amendment request: The amendment made changes to the
Seabrook Emergency Plan associated with the initiating conditions
involving a loss of safety system annunciation or indication in the
control room. The amendment revises the emergency action levels (EALs)
to include radiation monitoring indications within the aggregate of
safety system indications that are considered when evaluating a loss of
safety system indications rather than separate EALs.
Date of issuance: January 31, 2013.
Effective date: As of its date of issuance and shall be implemented
within 90 days.
Amendment No.: 133.
Facility Operating License No. NPF-86: The amendment revised the
License.
Date of initial notice in Federal Register: May 29, 2012 (77 FR
31661).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 31, 2013.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota (NSPM), Docket No. 50-263,
Monticello Nuclear Generating Plant (MNGP), Wright County, Minnesota
Date of application for amendment: May 8, 2012.
Brief description of amendment: The amendment revises the Technical
Specification, Section 3.3.1.1, ``Reactor Protection System (RPS)
Instrumentation,'' requirements pertaining to the Average Power Range
Monitors (APRMs). Specifically, it allows a time period for restoration
before declaring the channels inoperable when the absolute difference
between the APRM channel power and calculated thermal power exceeds the
limit of Technical Specification Surveillance Requirement 3.3.1.2.
Date of issuance: January 25, 2013.
Effective date: This license amendment is effective as of the date
of its issuance, and shall be implemented within 90 days of issuance.
Amendment No.: 171.
Facility Operating License No. DPR-22. Amendment revises the
Renewed Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: July 24, 2012 (77 FR
43378).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 25, 2013.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue
County, Minnesota
Date of application for amendments: October 27, 2009, as
supplemented by letters dated April 29, May 25, June 23, August 12, and
December 17 of 2010; June 22, July 11, August 9, and December 8 of
2011; February 13, February 24, and September 13 of 2012.
Brief description of amendments: These amendments modify the
Prairie Island Nuclear Generating Plant, Units 1
[[Page 11696]]
and 2, Technical Specifications (TSs) and licensing basis that supports
a full scope implementation of the Alternative Source Term Methodology.
The amendments also incorporate TS Task Force-490, ``Deletion of E-Bar
Definition and Revision to RCS [Reactor Coolant System] Specific
Activity Tech Spec,'' Revision 0.
Date of issuance: January 22, 2013.
Effective date: As of the date of issuance. The license conditions
shall be implemented within 30 days. The balance of the license
amendment shall be implemented in accordance with the terms of the
license conditions.
Amendment Nos.: 206, 193.
Renewed Facility Operating License Nos. DPR-42 and DPR-60:
Amendments revised the Facility Operating Licenses, Appendix B, and the
Technical Specifications.
Date of initial notice in Federal Register: April 6, 2010 (75 FR
17466). The supplemental letters contained clarifying information and
did not change the initial no significant hazards consideration
determination, and did not expand the scope of the original Federal
Register notice.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 22, 2013.
No significant hazards consideration comments received: No.
Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo
Canyon Nuclear Power Plant, Units 1 and 2, San Luis Obispo County,
California
Date of application for amendment: June 1, 2011, as supplemented by
letters dated February 6, May 31, August 6, and November 1, 2012.
Brief description of amendment: The amendments revised Technical
Specifications (TS) 3.7.5, ``Auxiliary Feedwater (AFW) System,'' 3.6.6,
``Containment Spray and Cooling Systems,'' 3.8.1, ``AC Sources--
Operating,'' 3.8.9, ``Distribution Systems--Operating,'' and Example
1.3-3 to clarify the operability of an AFW train during alternate
alignments; establish conditions, required actions, and completion
times when one steam supply to the turbine driven AFW pump is
inoperable concurrent with an inoperable motor driven AFW train; and
remove second completion times from TSs. These changes are consistent
with the guidance provided in Technical Specifications Task Force
(TSTF) Travelers TSTF-245, Revision 1, ``AFW Train Operable when in
Service,'' TSTF-340, Revision 3, ``Allow 7 day completion Time for a
Turbine-driven AFW Pump Inoperable,'' TSTF-412, Revision 3, ``Provide
Actions for One Steam Supply to Turbine Driven AFW/EFW Pump
Inoperable,'' and TSTF-439, Revision 2, ``Eliminate Second Completion
Times Limiting Time From Discovery of Failure to Meet an LCO.''
Date of issuance: January 31, 2013.
Effective date: As of its date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment Nos.: Unit 1-215; Unit 2-217.
Facility Operating License Nos. DPR-80 and DPR-82: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: December 31, 2011 (76
FR 77569). The supplemental letters dated February 6, May 31, August 6,
and November 1, 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.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 31, 2013.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, et al., Docket Nos. 50-280 and 50-
281, Surry Power Station, Units 1 and 2, Surry County, Virginia
Date of application for amendments: July 28, 2012.
Brief Description of amendments: These amendments revise Limiting
Condition for Operation (LCO) 3.1.H, ``Steam Generator (SG) Tube
Integrity,'' Specification 6.4.Q, ``Steam Generator (SG) Program,'' and
Specification 6.6.A.3, ``Steam Generator Tube Inspection Report,'' and
include technical specification (TS) Bases changes that summarize and
clarify the purpose of the TS in accordance with TS Task Force Traveler
(TSTF) 510, ``Revision to Steam Generator Program Inspection
Frequencies and Tube Sample Selection.''
Date of issuance: January 28, 2013.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment Nos.: 278, 278.
Renewed Facility Operating License Nos. DPR-32 and DPR-37:
Amendments change the licenses and the technical specifications.
Date of initial notice in Federal Register: October 16, 2012 (77 FR
63351). The supplements dated November 6, 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.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 28, 2013.
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 30, December 13, 2012.
Brief description of amendment: The amendments revised the North
Anna Technical Specifications (TSs) regarding steam generator tube
inspections and reporting as described in TSTF-510, Revision 2,
``Revision to Steam Generator Program Inspection Frequencies and Tube
Sample Selection.'' The changes are consistent with NRC-approved
Industry TSTF Standard Technical Specifications change TSTF-510,
Revision 2.
Date of issuance: January 28, 2013.
Effective date: As of the date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment Nos.: Unit 1-269 and Unit 2-250.
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: October 2, 2012 (77 FR
60155). The supplement dated December 13, 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.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 28, 2013.
No significant hazards consideration comments received: No.
[[Page 11697]]
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses and Final Determination of No Significant Hazards
Consideration and Opportunity for a Hearing (Exigent Public
Announcement or Emergency Circumstances)
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 for the
amendment 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.
Because of exigent or emergency circumstances associated with the
date the amendment was needed, there was not time for the Commission to
publish, for public comment before issuance, its usual notice of
consideration of issuance of amendment, proposed no significant hazards
consideration determination, and opportunity for a hearing.
For exigent circumstances, the Commission has either issued a
Federal Register notice providing opportunity for public comment or has
used local media to provide notice to the public in the area
surrounding a licensee's facility of the licensee's application and of
the Commission's proposed determination of no significant hazards
consideration. The Commission has provided a reasonable opportunity for
the public to comment, using its best efforts to make available to the
public means of communication for the public to respond quickly, and in
the case of telephone comments, the comments have been recorded or
transcribed as appropriate and the licensee has been informed of the
public comments.
In circumstances where failure to act in a timely way would have
resulted, for example, in derating or shutdown of a nuclear power plant
or in prevention of either resumption of operation or of increase in
power output up to the plant's licensed power level, the Commission may
not have had an opportunity to provide for public comment on its no
significant hazards consideration determination. In such case, the
license amendment has been issued without opportunity for comment. If
there has been some time for public comment but less than 30 days, the
Commission may provide an opportunity for public comment. If comments
have been requested, it is so stated. In either event, the State has
been consulted by telephone whenever possible.
Under its regulations, the Commission may issue and make an
amendment immediately effective, notwithstanding the pendency before it
of a request for a hearing from any person, in advance of the holding
and completion of any required hearing, where it has determined that no
significant hazards consideration is involved.
The Commission has applied the standards of 10 CFR 50.92 and has
made a final determination that the amendment involves no significant
hazards consideration. The basis for this determination is contained in
the documents related to this action. Accordingly, the amendments have
been issued and made effective 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 51.12(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
application for amendment, (2) the amendment to Facility Operating
License or Combined License, as applicable, 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 electronically through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at https://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
pdr.resource@nrc.gov.
The Commission is also offering an opportunity for a hearing with
respect to the issuance of the amendment. 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 or combined license. Requests for a hearing
and a petition for leave to intervene shall be filed in accordance with
the Commission's ``Agency Rules of Practice and Procedures'' 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, and electronically on the Internet at the NRC's Web
site, https://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are
problems in accessing the document, contact the PDR's Reference staff
at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov.
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 petitioner
intends to
[[Page 11698]]
rely in proving the contention at the hearing. The petitioner must also
provide references to those specific sources and documents of which the
petitioner is aware and on which the 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
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 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. Since the Commission has made a final determination that the
amendment involves no significant hazards consideration, if a hearing
is requested, it will not stay the effectiveness of the amendment. Any
hearing held would take place while the amendment is in effect.
All documents filed in the 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 hearing.docket@nrc.gov, 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 NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in NRC's ``Guidance for Electronic
Submission,'' which is available on the agency's public Web site at
https://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 https://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 guidance
available on the NRC's public Web site at https://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 https://www.nrc.gov/site-help/e-submittals.html, by email at
MSHD.Resource@nrc.gov, 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
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social
[[Page 11699]]
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.
Calvert Cliffs Nuclear Power Plant, LLC, Docket No. 50-318, Calvert
Cliffs Nuclear Power Plant, Unit 2, Calvert County, Maryland
Date of amendment request: January 22, 2013, as supplemented by
letter dated January 24, 2013.
Description of amendment request: The amendment revised Appendix C
of the Renewed Facility Operating License by adding a license condition
for Technical Specification 3.6.6, which will allow the ``B'' train of
the Containment Cooling System to be considered operable with a single
containment cooling fan and cooler by limiting the refueling water
storage tank water temperature, containment average air temperature,
containment air pressure, and saltwater inlet temperature for the
period from January 26, to February 17, 2013.
Date of issuance: January 25, 2013.
Effective date: As of the date of issuance, and shall be
implemented within 30 days.
Amendment No.: 280.
Renewed Facility Operating License No. DPR-69: Amendment revised
the License and Appendix C.
Public comments requested as to proposed no significant hazards
consideration (NSHC): No. The Commission's related evaluation of the
amendment, finding of emergency circumstances, state consultation, and
final NSHC determination are contained in a safety evaluation dated
January 25, 2013.
Attorney for licensee: Steven L. Miller, General Counsel,
Constellation Energy Nuclear Group, LLC, 100 Constellation Way, Suite
200c, Baltimore, MD 21202.
NRC Branch Chief: George Wilson.
Dated at Rockville, Maryland, this 8th day of February 2013.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2013-03582 Filed 2-15-13; 8:45 am]
BILLING CODE 7590-01-P
