Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information, 6645-6651 [2014-01597]
Download as PDF
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
Safety Evaluation dated January 14,
2014.
No significant hazards consideration
comments received: None.
mstockstill on DSK4VPTVN1PROD with NOTICES
Union Electric Company, Docket No.
50–483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of application for amendment:
August 29, 2011, as supplemented by
letters dated November 9, 2011, April 17
and July 12, 2012, and February 19,
August 5, September 24, and December
19, 2013.
Brief description of amendment: The
amendment transitions the Callaway
Plant fire protection program to a riskinformed, performance-based program
based on the National Fire Protection
Association (NFPA) 805, in accordance
with 10 CFR 50.48(c). The NFPA 805
allows the use of performance-based
methods such as fire modeling and riskinformed methods such as fire
probabilistic risk assessment to
demonstrate compliance with the
nuclear safety performance criteria.
Date of issuance: January 13, 2014.
Effective date: As of its date of
issuance and shall be implemented by 8
months from the date of issuance.
Amendment No.: 206.
Facility Operating License No. NPF–
30: The amendment revised the
Operating License and Technical
Specifications.
Date of initial notice in Federal
Register :February 14, 2012 (77 FR
8294). The supplements dated
November 9, 2011, April 17 and July 12,
2012, and February 19, August 5,
September 24, and December 19, 2013,
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 13,
2014.
No significant hazards consideration
comments received: No.
Union Electric Company, Docket No.
50–483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of application for amendment:
December 20, 2012, as supplemented by
letters dated June 6 and August 29,
2013.
Brief description of amendment: The
amendment revised a methodology in
the licensing basis as described in the
Final Safety Analysis Report—Standard
Plant to include damping values for the
seismic design and analysis of the
VerDate Mar<15>2010
20:48 Feb 03, 2014
Jkt 232001
integrated head assembly that are
consistent with the recommendations of
the NRC’s Regulatory Guide 1.61,
‘‘Damping Values for Seismic Design of
Nuclear Power Plants,’’ Revision 1,
March 2007.
Date of issuance: January 14, 2014.
Effective date: As of its date of
issuance and shall be implemented
within 90 days from the date of
issuance.
Amendment No.: 207.
Facility Operating License No. NPF–
30: The amendment revised the
Operating License.
Date of initial notice in Federal
Register: March 4, 2013 (78 FR 14139).
The supplemental letters dated June 6
and August 29, 2013, 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 14,
2014.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 24th day
of January 2014.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2014–02048 Filed 2–3–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Applications and Amendments to
Facility Operating Licenses and
Combined Licenses Involving
Proposed No Significant Hazards
Considerations and Containing
Sensitive Unclassified Non-Safeguards
Information and Order Imposing
Procedures for Access to Sensitive
Unclassified Non-Safeguards
Information
Nuclear Regulatory
Commission.
ACTION: License amendment request;
opportunity to comment, request a
hearing, and petition for leave to
intervene; order.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) received and is
considering approval of two amendment
PO 00000
Frm 00115
Fmt 4703
Sfmt 4703
requests. The amendment requests are
for Turkey Point Nuclear Generating,
Units 3 and 4; and Seabrook Station,
Unit 1. For each amendment request,
the NRC proposes to determine that they
involve no significant hazards
consideration. In addition, each
amendment request contains sensitive
unclassified non-safeguards information
(SUNSI).
DATES: Comments must be filed by
March 6, 2014. A request for a hearing
must be filed by April 7, 2014. Any
potential party as defined in § 2.4 of
Title 10 of the Code of Federal
Regulations (10 CFR), who believes
access to SUNSI is necessary to respond
to this notice must request document
access by February 14, 2014.
ADDRESSES: You may submit comment
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2014–0008. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: 3WFN, 06–
44M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
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
[NRC–2014–0008]
SUMMARY:
6645
A. Accessing Information
Please refer to Docket ID NRC–2014–
0008 when contacting the NRC about
the availability of information regarding
this document. You may access
publicly-available information related to
this action by the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2014–0008.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publiclyavailable 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
E:\FR\FM\04FEN1.SGM
04FEN1
6646
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced in this notice (if
that document is available in ADAMS)
is provided the first time that a
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.
B. Submitting Comments
Please include Docket ID NRC–2014–
0008 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
you do not want to be publicly
disclosed in your comment submission.
The NRC posts all comment
submissions at https://
www.regulations.gov as well as entering
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.
mstockstill on DSK4VPTVN1PROD with NOTICES
II. Background
Pursuant to Section 189a.(2) of the
Atomic Energy Act of 1954, as amended
(the Act), the NRC is publishing this
notice. The Act requires the
Commission to 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 notice includes notices of
amendments containing SUNSI.
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
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
10 CFR 50.92, this means that operation
of the facility in accordance with the
proposed amendment would not (1)
involve a significant increase in the
probability or consequences of an
accident previously evaluated, 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 ML14007A219
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
PO 00000
Frm 00116
Fmt 4703
Sfmt 4703
intervene shall be filed in accordance
with the Commission’s ‘‘Agency Rules
of Practice and Procedure’’ in 10 CFR
Part 2. Interested person(s) should
consult a current copy of 10 CFR 2.309,
which is available at the NRC’s PDR,
located at One White Flint North, Room
O1–F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. The
NRC’s regulations are accessible
electronically from the NRC Library on
the NRC’s Web site at https://
www.nrc.gov/reading-rm/doccollections/cfr/. If a request for a hearing
or petition for leave to intervene is filed
within 60 days, 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 set forth the specific
contentions which the requestor/
petitioner seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the requestor/petitioner shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the requestor/petitioner
intends to rely in proving the contention
at the hearing. The requestor/petitioner
must also provide references to those
specific sources and documents of
which the petitioner is aware and on
which the requestor/petitioner intends
to rely to establish those facts or expert
opinion. The petition must include
sufficient information to show that a
E:\FR\FM\04FEN1.SGM
04FEN1
mstockstill on DSK4VPTVN1PROD with NOTICES
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
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, and the
Commission has not made a final
determination on the issue of no
significant hazards consideration, the
Commission will make a final
determination on the issue of no
significant hazards consideration. The
final determination will serve to decide
when the hearing is held. If the final
determination is that the amendment
request involves no significant hazards
consideration, the Commission may
issue the amendment and make it
immediately effective, notwithstanding
the request for a hearing. Any hearing
held would take place after issuance of
the amendment. If the final
determination is that the amendment
request involves a significant hazards
consideration, then any hearing held
would take place before the issuance of
any amendment.
All documents filed in NRC’s
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 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
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
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 public
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/sitehelp/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/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
PO 00000
Frm 00117
Fmt 4703
Sfmt 4703
6647
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/esubmittals.html, by email to
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
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 NRC’s
E:\FR\FM\04FEN1.SGM
04FEN1
6648
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
Description of amendment request:
This amendment request contains
sensitive unclassified non-safeguards
information (SUNSI). The licensee
requests NRC review and approval for
adoption of a new fire protection
licensing basis for the Turkey Point
Nuclear Generating, Units 3 and 4 (PTN,
which is a licensee designation for the
plant). The request was submitted in
accordance with the requirements in 10
CFR 50.48(a) and (c), and the guidance
in Regulatory Guide (RG) 1.205,
Revision 1, ‘‘Risk-Informed
Performance-Based Fire Protection for
Existing Light-Water Nuclear Power
Plants,’’ dated December 2009 (ADAMS
Accession No. ML092730314). The
licensee’s request follows the Nuclear
Energy Institute (NEI) methodology in
Revision 2 of NEI 04–02, ‘‘Guidance for
Implementing a Risk-Informed,
Performance-Based Fire Protection
Program under 10 CFR 50.48(c),’’ dated
April 2008 (ADAMS Accession No.
ML081130188). The request includes
the methodology used to demonstrate
compliance with and transition to the
National Fire Protection Association
(NFPA) 805, ‘‘Performance-Based
Standard for Fire Protection for Light
Water Reactor Electric Generating
Plants,’’ 2001 Edition. Copies of NFPA
805 may be purchased from the NFPA
Customer Service Department, 1
Batterymarch Park, P.O. Box 9101,
Quincy, Massachusetts 02269–9101 and
in PDF format through the NFPA Online
Catalog (https://www.nfpa.org) or by
calling 1–800–344–3555 or 617–770–
3000. Copies are also available for
inspection at the NRC’s Library, Two
White Flint North, 11545 Rockville
Pike, Rockville, Maryland 20852–2738,
and at the NRC’s PDR, One White Flint
North, Room O1–F15, 11555 Rockville
Pike, Rockville, Maryland, 20852–2738.
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 as
follows:
Florida Power and Light Company,
Docket Nos. 50–250 and 50–251, Turkey
Point Nuclear Generating, Units 3 and
4, Miami-Dade County, Florida
mstockstill on DSK4VPTVN1PROD with NOTICES
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. However, a request to
intervene will require including
information on local residence in order
to demonstrate a proximity assertion of
interest in the proceeding. 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 three factors in 10 CFR
2.309(c)(1)(i)–(iii).
For further details with respect to this
amendment action, 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. 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.
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
Operation of PTN in accordance with the
proposed amendment does not increase the
probability or consequences of accidents
previously evaluated. The Updated Final
Safety Analysis Report (UFSAR) documents
the analyses of design basis accidents (DBAs)
at PTN. The proposed amendment does not
adversely affect accident initiators nor alter
design assumptions, conditions, or
configurations of the facility and does not
adversely affect the ability of structures,
Date of amendment request: June 28,
2012 (publicly available version is in
ADAMS at Accession No.
ML12191A048), as supplemented by
letters dated September 19, 2012, March
18, 2013, April 16, 2013, and May 15,
2013 (ADAMS Accession Nos.
ML12278A106, ML13099A441,
ML13109A008, and ML13157A011,
respectively).
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
PO 00000
Frm 00118
Fmt 4703
Sfmt 4703
systems, and components (SSCs) to perform
their design function. The SSCs required to
safely shut down the reactor and to maintain
it in a safe shutdown (SSD) condition will
remain capable of performing their design
functions.
The purpose of this amendment is to
permit PTN to adopt a new fire protection
licensing basis which complies with the
requirements in 10 CFR 50.48(a) and (c) and
the guidance of Regulatory Guide (RG) 1.205,
Revision 1. The NRC considers that the
NFPA 805 provides an acceptable
methodology and performance criteria for
licensees to identify fire protection systems
and features that are an acceptable alternative
to the 10 CFR Part 50, Appendix R fire
protection features (69 FR 33536; June 16,
2004). Engineering analyses, in accordance
with NFPA 805, have been performed to
demonstrate that the risk-informed,
performance-based (RI–PB) requirements per
NFPA 805 have been met.
The NFPA 805, taken as a whole, provides
an acceptable alternative to 10 CFR 50.48(b)
and satisfies 10 CFR 50.48(a) and General
Design Criterion 3 of Appendix A to 10 CFR
Part 50 and meets the underlying intent of
the NRC’s existing fire protection regulations
and guidance, achieves defense-in-depth
(DID) and the goals, performance objectives,
and performance criteria specified in Chapter
1 of the standard. The small increase in net
change in core damage frequency associated
with this License Amendment Request (LAR)
submittal is consistent with the
Commission’s Safety Goal Policy.
Additionally, 10 CFR 50.48(c) allows selfapproval of fire protection program changes
post-transition. If there are any increases
post-transition in core damage frequency or
risk, the increase will be small and consistent
with the intent of the Commission’s Safety
Goal Policy.
Based on this, the implementation of this
amendment does not significantly increase
the probability of any accident previously
evaluated. Equipment required to mitigate an
accident remains capable of performing the
assumed function.
Therefore, the consequences of any
accident previously evaluated are not
significantly increased with the
implementation of this amendment.
2. Does the proposed amendment create
the possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
Operation of PTN in accordance with the
proposed amendment does not create the
possibility of a new or different kind of
accident from any accident previously
evaluated. Any scenario or previously
analyzed accident with offsite dose was
included in the evaluation of DBAs
documented in the UFSAR. The proposed
change does not alter the requirements or
function for systems required during accident
conditions. Implementation of the new fire
protection licensing basis which complies
with the requirements in 10 CFR 50.48(a) and
(c) and the guidance of RG 1.205, Revision
1 will not result in new or different
accidents.
The proposed amendment does not
adversely affect accident initiators nor alter
E:\FR\FM\04FEN1.SGM
04FEN1
mstockstill on DSK4VPTVN1PROD with NOTICES
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
design assumptions, conditions, or
configurations of the facility. The proposed
amendment does not adversely affect the
ability of SSCs to perform their design
function. The SSCs required to safely shut
down the reactor and maintain it in a safe
shutdown condition remain capable of
performing their design functions.
The purpose of this amendment is to
permit PTN to adopt a new fire protection
licensing basis which complies with the
requirements in 10 CFR 50.48(a) and (c) and
the guidance of RG 1.205, Revision 1. The
NRC considers that NFPA 805 provides an
acceptable methodology and performance
criteria for licensees to identify fire
protection systems and features that are an
acceptable alternative to the 10 CFR Part 50,
Appendix R fire protection features (69 FR
33536; June 16, 2004).
The requirements in NFPA 805 address
only fire protection and the impacts of fire
on the plant that have already been
evaluated. Based on this, the implementation
of this amendment does not create the
possibility of a new or different kind of
accident from any kind of accident
previously evaluated. The proposed changes
do not involve new failure mechanisms or
malfunctions that can initiate a new accident.
Therefore, the possibility of a new or
different kind of accident from any kind of
accident previously evaluated is not created
with the implementation of this amendment.
3. Does the proposed amendment involve
a significant reduction in the margin of
safety?
Response: No.
Operation of PTN in accordance with the
proposed amendment does not involve a
significant reduction in the margin of safety.
The proposed amendment does not alter the
manner in which safety limits, limiting safety
system settings or limiting conditions for
operation are determined. The safety analysis
acceptance criteria are not affected by this
change. The proposed amendment does not
adversely affect existing plant safety margins
or the reliability of equipment assumed to
mitigate accidents in the UFSAR. The
proposed amendment does not adversely
affect the ability of SSCs to perform their
design function. The SSCs required to safely
shut down the reactor and to maintain it in
a safe shutdown condition remain capable of
performing their design function.
The purpose of this amendment is to
permit PTN to adopt a new fire protection
licensing basis which complies with the
requirements in 10 CFR 50.48(a) and (c) and
the guidance of RG 1.205, Revision 1. The
NRC considers that NFPA 805 provides an
acceptable methodology and performance
criteria for licensees to identify fire
protection systems and features that are an
acceptable alternative to the 10 CFR Part 50,
Appendix R fire protection features (69 FR
33536; June 16, 2004). Engineering analyses,
which may include engineering evaluations,
probabilistic safety assessments, and fire
modeling calculations, have been performed
to demonstrate that the performance-based
methods do not result in a significant
reduction in the margin of safety.
Based on this, the implementation of this
amendment does not significantly reduce the
VerDate Mar<15>2010
20:42 Feb 03, 2014
Jkt 232001
margin of safety. The proposed changes are
evaluated to ensure that the risk and safety
margins are kept within acceptable limits.
Therefore, the transition does not involve
a significant reduction in the margin of
safety.
The NFPA 805 continues to protect public
health and safety and the common defense
and security because the overall approach of
NFPA 805 is consistent with the key
principles for evaluating license basis
changes, as described in RG 1.174, is
consistent with the DID philosophy, and
maintains sufficient safety margins.
Margins previously established for the PTN
program in accordance with 10 CFR 50.48(b)
and Appendix R to 10 CFR Part 50 are not
significantly reduced.
Therefore, this LAR does not result in a
reduction in a margin of safety.
The NRC staff 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: William S.
Blair, Managing Attorney—Nuclear,
Florida Power & Light, 700 Universe
Blvd., MS LAW/JB, Juno Beach, Florida,
33408–0420.
NRC Branch Chief: Jessie F.
Quichocho.
NextEra Energy Seabrook, LLC., Docket
No. 50–443, Seabrook Station, Unit 1,
Rockingham County, New Hampshire
Date of amendment request:
September 10, 2013. A publicly
available version is in ADAMS under
Accession No. ML13260A160.
Description of amendment request:
This amendment request contains
sensitive unclassified non-safeguards
information (SUNSI). The proposed
amendment will modify the Seabrook
Technical Specifications (TSs).
Specifically, the proposed amendment
will revise TS 6.8.1.6.b, ‘‘Core Operating
Limits Report,’’ by adding Areva
Licensing Report ANP–3243P,
‘‘Seabrook Station, Unit 1 Fixed Incore
Detector System Analysis Supplement
to YAEC–1855PA,’’ dated July 31, 2013
(a publicly available version is in
ADAMS under Accession No.
ML13260A161), which supplements
and modifies the previously approved
methodology. The proposed change also
modifies the surveillance requirements
associated with the heat flux hot
channel factor and nuclear enthalpy rise
hot channel factor to include revised
uncertainty values when measurement
is obtained using the fixed incore
detector system (FIDS).
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
PO 00000
Frm 00119
Fmt 4703
Sfmt 4703
6649
licensee has provided its analysis of the
issue of no significant hazards
consideration, which is presented
below, along with the NRC’s edits in
square brackets:
1. Does the proposed change involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The FIDS is used for core surveillances to
provide confirmatory information on the
neutron flux distribution of the core. This
system is not used for accident mitigation
and does not provide any automatic control
functions or protective functions for the
operation of the plant.
As the proposed change does not involve
any changes to the physical equipment or
operation of the system, there is no increase
in the probability of an accident previously
evaluated.
The proposed Technical Specification (TS)
change determines a revised uncertainty
value for the FQ [heat flux hot channel factor]
and FΔh [nuclear enthalpy rise hot channel
factor] TS surveillance parameters. ANP–
3243P, ‘‘Seabrook Station Unit 1 Fixed Incore
Detector System Analysis Supplement to
YAEC–1855PA,’’ documents that these
modifications yield results in surveillance
parameters that compare well to the original
methodology over the first 8 cycles. The
report also documents that the results of the
uncertainty analysis using all 15 completed
cycles compared well to the results of the
uncertainty analysis for the original YAEC–
1855PA methodology. The report concludes
that the revised FIDS analysis methodology
remains comparable in accuracy and
functionality to the original YAEC–1855PA
methodology and the moveable incore
detector system.
Therefore, the proposed change does not
involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the
possibility of a new or different kind of
accident from any previously evaluated?
Response: No.
The operation of the facility in accordance
with the proposed amendment does not
create the possibility of a new or different
kind of accident from any accident
previously evaluated since the proposed
change will not affect plant safety analysis
assumptions or the physical design of the
facility. The revised uncertainty applied to
the measured core peaking factors ensures
the safety limits are maintained; hence, no
new failure mode is introduced.
Therefore, the proposed changes do 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.
Margin of safety is associated with
confidence in the ability of the fission
product barriers (i.e., fuel cladding, reactor
coolant system pressure boundary, and
containment structure) to limit the level of
radiation dose to the public. The proposed
E:\FR\FM\04FEN1.SGM
04FEN1
6650
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
changes to modify the FIDS methodology and
provide revised uncertainty values for the FQ
and FΔh TS surveillance parameters do not
involve a significant change in the method of
plant operation, and no accident analyses
will be affected by the proposed changes.
Additionally, the proposed changes will not
relax any criteria used to establish safety
limits and will not relax any safety system
settings. The safety analysis acceptance
criteria are not affected by this change. The
proposed change will not result in plant
operation in a configuration outside the
design basis. The proposed change does not
adversely affect systems that respond to
safely shutdown the plant and to maintain
the plant in a safe shutdown condition.
Therefore, the proposed changes do 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. James Petro,
Managing Attorney, Florida Power &
Light Company, P.O. Box 14000, Juno
Beach, Florida, 33408–0420.
Acting NRC Branch Chief: John G.
Lamb.
mstockstill on DSK4VPTVN1PROD with NOTICES
Order Imposing Procedures for Access
to Sensitive Unclassified NonSafeguards Information for Contention
Preparation
Florida Power and Light Company,
Docket Nos. 50–250 and 50–251, Turkey
Point Nuclear Generating, Units 3 and
4, Miami-Dade County, Florida; NextEra
Energy Seabrook, LLC., Docket No. 50–
443, Seabrook Station, Unit 1,
Rockingham County, New Hampshire
A. This Order contains instructions
regarding how potential parties to this
proceeding may request access to
documents containing SUNSI.
B. Within 10 days after publication of
this notice of hearing and opportunity to
petition for leave to intervene, any
potential party who believes access to
SUNSI is necessary to respond to this
notice may request such access. A
‘‘potential party’’ is any person who
intends to participate as a party by
demonstrating standing and filing an
admissible contention under 10 CFR
2.309. Requests for access to SUNSI
submitted later than 10 days after
publication of this notice will not be
considered absent a showing of good
cause for the late filing, addressing why
the request could not have been filed
earlier.
C. The requestor shall submit a letter
requesting permission to access SUNSI
to the Office of the Secretary, U.S.
VerDate Mar<15>2010
20:42 Feb 03, 2014
Jkt 232001
Nuclear Regulatory Commission,
Washington, DC 20555–0001, Attention:
Rulemakings and Adjudications Staff,
and provide a copy to the Associate
General Counsel for Hearings,
Enforcement and Administration, Office
of the General Counsel, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001. The expedited delivery
or courier mail address for both offices
is: U.S. Nuclear Regulatory Commission,
11555 Rockville Pike, Rockville,
Maryland 20852. The email address for
the Office of the Secretary and the
Office of the General Counsel are
Hearing.Docket@nrc.gov and
OGCmailcenter@nrc.gov, respectively.1
The request must include the following
information:
(1) A description of the licensing
action with a citation to this Federal
Register notice;
(2) The name and address of the
potential party and a description of the
potential party’s particularized interest
that could be harmed by the action
identified in C.(1); and
(3) The identity of the individual or
entity requesting access to SUNSI and
the requestor’s basis for the need for the
information in order to meaningfully
participate in this adjudicatory
proceeding. In particular, the request
must explain why publicly available
versions of the information requested
would not be sufficient to provide the
basis and specificity for a proffered
contention.
D. Based on an evaluation of the
information submitted under paragraph
C.(3) the NRC staff will determine
within 10 days of receipt of the request
whether:
(1) There is a reasonable basis to
believe the petitioner is likely to
establish standing to participate in this
NRC proceeding; and
(2) The requestor has established a
legitimate need for access to SUNSI.
E. If the NRC staff determines that the
requestor satisfies both D.(1) and D.(2)
above, the NRC staff will notify the
requestor in writing that access to
SUNSI has been granted. The written
notification will contain instructions on
how the requestor may obtain copies of
the requested documents, and any other
conditions that may apply to access to
those documents. These conditions may
include, but are not limited to, the
signing of a Non-Disclosure Agreement
or Affidavit, or Protective Order 2 setting
forth terms and conditions to prevent
the unauthorized or inadvertent
disclosure of SUNSI by each individual
who will be granted access to SUNSI.
F. Filing of Contentions. Any
contentions in these proceedings that
are based upon the information received
as a result of the request made for
SUNSI must be filed by the requestor no
later than 25 days after the requestor is
granted access to that information.
However, if more than 25 days remain
between the date the petitioner is
granted access to the information and
the deadline for filing all other
contentions (as established in the notice
of hearing or opportunity for hearing),
the petitioner may file its SUNSI
contentions by that later deadline. This
provision does not extend the time for
filing a request for a hearing and
petition to intervene, which must
comply with the requirements of 10 CFR
2.309.
G. Review of Denials of Access.
(1) If the request for access to SUNSI
is denied by the NRC staff after a
determination on standing and need for
access, the NRC staff shall immediately
notify the requestor in writing, briefly
stating the reason or reasons for the
denial.
(2) The requestor may challenge the
NRC staff’s adverse determination by
filing a challenge within 5 days of
receipt of that determination with: (a)
The presiding officer designated in this
proceeding; (b) if no presiding officer
has been appointed, the Chief
Administrative Judge, or if he or she is
unavailable, another administrative
judge, or an administrative law judge
with jurisdiction pursuant to 10 CFR
2.318(a); or (c) if another officer has
been designated to rule on information
access issues, with that officer.
H. Review of Grants of Access. A
party other than the requestor may
challenge an NRC staff determination
granting access to SUNSI whose release
would harm that party’s interest
independent of the proceeding. Such a
challenge must be filed with the Chief
Administrative Judge within 5 days of
the notification by the NRC staff of its
grant of access.
If challenges to the NRC staff
determinations are filed, these
procedures give way to the normal
process for litigating disputes
concerning access to information. The
availability of interlocutory review by
1 While a request for hearing or petition to
intervene in this proceeding must comply with the
filing requirements of the NRC’s ‘‘E-Filing Rule,’’
the initial request to access SUNSI under these
procedures should be submitted as described in this
paragraph.
2 Any motion for Protective Order or draft NonDisclosure Affidavit or Agreement for SUNSI must
be filed with the presiding officer or the Chief
Administrative Judge if the presiding officer has not
yet been designated, within 30 days of the deadline
for the receipt of the written access request.
PO 00000
Frm 00120
Fmt 4703
Sfmt 4703
E:\FR\FM\04FEN1.SGM
04FEN1
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
the Commission of orders ruling on
such NRC staff determinations (whether
granting or denying access) is governed
by 10 CFR 2.311.3
I. The Commission expects that the
NRC staff and presiding officers (and
any other reviewing officers) will
consider and resolve requests for access
to SUNSI, and motions for protective
orders, in a timely fashion in order to
minimize any unnecessary delays in
identifying those petitioners who have
standing and who have propounded
contentions meeting the specificity and
basis requirements in 10 CFR Part 2.
Attachment 1 to this Order summarizes
the general target schedule for
processing and resolving requests under
these procedures.
It is so ordered.
6651
Dated at Rockville, Maryland, this 22nd
day of January 2014.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
ATTACHMENT 1—General Target
Schedule for Processing and Resolving
Requests for Access to Sensitive
Unclassified Non-Safeguards
Information in This Proceeding
Day
Event/activity
0 ........................
Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests.
Deadline for submitting requests for access to Sensitive Unclassified Non-Safeguards Information (SUNSI) with information:
supporting the standing of a potential party identified by name and address; describing the need for the information in order
for the potential party to participate meaningfully in an adjudicatory proceeding.
Deadline for submitting petition for intervention containing: (i) Demonstration of standing; and (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestor reply).
Nuclear Regulatory Commission (NRC) staff informs the requestor of the staff’s determination whether the request for access
provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also informs
any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document processing
(preparation of redactions or review of redacted documents).
If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for requestor/petitioner to file a motion seeking a ruling
to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief
Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any
party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to
file a motion seeking a ruling to reverse the NRC staff’s grant of access.
Deadline for NRC staff reply to motions to reverse NRC staff determination(s).
(Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and
file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/licensee to file Non-Disclosure
Agreement for SUNSI.
If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access
to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a
final adverse determination by the NRC staff.
Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order.
Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days
remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as
established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later
deadline.
(Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI.
(Answer receipt +7) Petitioner/Intervenor reply to answers.
Decision on contention admission.
10 ......................
60 ......................
20 ......................
25 ......................
30 ......................
40 ......................
A .......................
A + 3 .................
A + 28 ...............
A + 53 ...............
A + 60 ...............
>A + 60 .............
[FR Doc. 2014–01597 Filed 2–3–14; 8:45 am]
Week of February 3, 2014
Thursday, February 20, 2014
BILLING CODE 7590–01–P
There are no meetings scheduled for
the week of February 3, 2014.
NUCLEAR REGULATORY
COMMISSION
Week of February 10, 2014—Tentative
9:30 a.m. Briefing on Threat
Environment Assessment (Closed—Ex.
1)
There are no meetings scheduled for
the week of February 10, 2014.
[NRC–2014–0001]
Week of February 17, 2014—Tentative
Sunshine Act Meeting Notice
Wednesday, February 19, 2014
Weeks of February 3, 10, 17, 24,
March 3, 10, 2014.
DATES:
Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
mstockstill on DSK4VPTVN1PROD with NOTICES
PLACE:
STATUS:
9:30 a.m. Briefing on NRC
International Activities (Closed—Ex. 1 &
9)
1:30 p.m. Briefing on Security Issues
(Closed—Ex. 3)
Public and Closed.
3 Requestors should note that the filing
requirements of the NRC’s E-Filing Rule (72 FR
49139; August 28, 2007) apply to appeals of NRC
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
staff determinations (because they must be served
on a presiding officer or the Commission, as
PO 00000
Frm 00121
Fmt 4703
Sfmt 4703
Week of February 24, 2014—Tentative
There are no meetings scheduled for
the week of February 24, 2014.
Week of March 3, 2014—Tentative
Monday, March 3, 2014
1:30 p.m. Briefing on Human
Reliability Program Activities and
Analyses (Public Meeting)
(Contact: Sean Peters, 301–251–7582)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
applicable), but not to the initial SUNSI request
submitted to the NRC staff under these procedures.
E:\FR\FM\04FEN1.SGM
04FEN1
Agencies
[Federal Register Volume 79, Number 23 (Tuesday, February 4, 2014)]
[Notices]
[Pages 6645-6651]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-01597]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2014-0008]
Applications and Amendments to Facility Operating Licenses and
Combined Licenses Involving Proposed No Significant Hazards
Considerations and Containing Sensitive Unclassified Non-Safeguards
Information and Order Imposing Procedures for Access to Sensitive
Unclassified Non-Safeguards Information
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment request; opportunity to comment, request a
hearing, and petition for leave to intervene; order.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is
considering approval of two amendment requests. The amendment requests
are for Turkey Point Nuclear Generating, Units 3 and 4; and Seabrook
Station, Unit 1. For each amendment request, the NRC proposes to
determine that they involve no significant hazards consideration. In
addition, each amendment request contains sensitive unclassified non-
safeguards information (SUNSI).
DATES: Comments must be filed by March 6, 2014. A request for a hearing
must be filed by April 7, 2014. Any potential party as defined in Sec.
2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who
believes access to SUNSI is necessary to respond to this notice must
request document access by February 14, 2014.
ADDRESSES: You may submit comment by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2014-0008. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: 3WFN, 06-44M, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
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-2014-0008 when contacting the NRC
about the availability of information regarding this document. You may
access publicly-available information related to this action by the
following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2014-0008.
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
[[Page 6646]]
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The
ADAMS accession number for each document referenced in this notice (if
that document is available in ADAMS) is provided the first time that a
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.
B. Submitting Comments
Please include Docket ID NRC-2014-0008 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 you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at https://www.regulations.gov as well as entering 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.
II. Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the NRC is publishing this notice. The Act requires
the Commission to 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 notice includes notices of amendments containing SUNSI.
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 10 CFR 50.92, this means that operation
of the facility in accordance with the proposed amendment would not (1)
involve a significant increase in the probability or consequences of an
accident previously evaluated, 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 ML14007A219 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 Procedure'' in 10 CFR Part 2. Interested
person(s) should consult a current copy of 10 CFR 2.309, which is
available at the NRC's PDR, located at One White Flint North, Room O1-
F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The
NRC's regulations are accessible 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 within 60 days, 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 set forth the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a
[[Page 6647]]
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, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to decide when the hearing is held. If the final determination is that
the amendment request involves no significant hazards consideration,
the Commission may issue the amendment and make it immediately
effective, notwithstanding the request for a hearing. Any hearing held
would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of any amendment.
All documents filed in NRC's 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 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
public 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's Web site
at https://www.nrc.gov/site-help/e-submittals.html, by email to
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
NRC's
[[Page 6648]]
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.
However, a request to intervene will require including information on
local residence in order to demonstrate a proximity assertion of
interest in the proceeding. 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 three factors in 10
CFR 2.309(c)(1)(i)-(iii).
For further details with respect to this amendment action, 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. 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.
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: June 28, 2012 (publicly available
version is in ADAMS at Accession No. ML12191A048), as supplemented by
letters dated September 19, 2012, March 18, 2013, April 16, 2013, and
May 15, 2013 (ADAMS Accession Nos. ML12278A106, ML13099A441,
ML13109A008, and ML13157A011, respectively).
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The licensee
requests NRC review and approval for adoption of a new fire protection
licensing basis for the Turkey Point Nuclear Generating, Units 3 and 4
(PTN, which is a licensee designation for the plant). The request was
submitted in accordance with the requirements in 10 CFR 50.48(a) and
(c), and the guidance in Regulatory Guide (RG) 1.205, Revision 1,
``Risk-Informed Performance-Based Fire Protection for Existing Light-
Water Nuclear Power Plants,'' dated December 2009 (ADAMS Accession No.
ML092730314). The licensee's request follows the Nuclear Energy
Institute (NEI) methodology in Revision 2 of NEI 04-02, ``Guidance for
Implementing a Risk-Informed, Performance-Based Fire Protection Program
under 10 CFR 50.48(c),'' dated April 2008 (ADAMS Accession No.
ML081130188). The request includes the methodology used to demonstrate
compliance with and transition to the National Fire Protection
Association (NFPA) 805, ``Performance-Based Standard for Fire
Protection for Light Water Reactor Electric Generating Plants,'' 2001
Edition. Copies of NFPA 805 may be purchased from the NFPA Customer
Service Department, 1 Batterymarch Park, P.O. Box 9101, Quincy,
Massachusetts 02269-9101 and in PDF format through the NFPA Online
Catalog (https://www.nfpa.org) or by calling 1-800-344-3555 or 617-770-
3000. Copies are also available for inspection at the NRC's Library,
Two White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852-
2738, and at the NRC's PDR, One White Flint North, Room O1-F15, 11555
Rockville Pike, Rockville, Maryland, 20852-2738.
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 as follows:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
Operation of PTN in accordance with the proposed amendment does
not increase the probability or consequences of accidents previously
evaluated. The Updated Final Safety Analysis Report (UFSAR)
documents the analyses of design basis accidents (DBAs) at PTN. The
proposed amendment does not adversely affect accident initiators nor
alter design assumptions, conditions, or configurations of the
facility and does not adversely affect the ability of structures,
systems, and components (SSCs) to perform their design function. The
SSCs required to safely shut down the reactor and to maintain it in
a safe shutdown (SSD) condition will remain capable of performing
their design functions.
The purpose of this amendment is to permit PTN to adopt a new
fire protection licensing basis which complies with the requirements
in 10 CFR 50.48(a) and (c) and the guidance of Regulatory Guide (RG)
1.205, Revision 1. The NRC considers that the NFPA 805 provides an
acceptable methodology and performance criteria for licensees to
identify fire protection systems and features that are an acceptable
alternative to the 10 CFR Part 50, Appendix R fire protection
features (69 FR 33536; June 16, 2004). Engineering analyses, in
accordance with NFPA 805, have been performed to demonstrate that
the risk-informed, performance-based (RI-PB) requirements per NFPA
805 have been met.
The NFPA 805, taken as a whole, provides an acceptable
alternative to 10 CFR 50.48(b) and satisfies 10 CFR 50.48(a) and
General Design Criterion 3 of Appendix A to 10 CFR Part 50 and meets
the underlying intent of the NRC's existing fire protection
regulations and guidance, achieves defense-in-depth (DID) and the
goals, performance objectives, and performance criteria specified in
Chapter 1 of the standard. The small increase in net change in core
damage frequency associated with this License Amendment Request
(LAR) submittal is consistent with the Commission's Safety Goal
Policy. Additionally, 10 CFR 50.48(c) allows self-approval of fire
protection program changes post-transition. If there are any
increases post-transition in core damage frequency or risk, the
increase will be small and consistent with the intent of the
Commission's Safety Goal Policy.
Based on this, the implementation of this amendment does not
significantly increase the probability of any accident previously
evaluated. Equipment required to mitigate an accident remains
capable of performing the assumed function.
Therefore, the consequences of any accident previously evaluated
are not significantly increased with the implementation of this
amendment.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
Operation of PTN in accordance with the proposed amendment does
not create the possibility of a new or different kind of accident
from any accident previously evaluated. Any scenario or previously
analyzed accident with offsite dose was included in the evaluation
of DBAs documented in the UFSAR. The proposed change does not alter
the requirements or function for systems required during accident
conditions. Implementation of the new fire protection licensing
basis which complies with the requirements in 10 CFR 50.48(a) and
(c) and the guidance of RG 1.205, Revision 1 will not result in new
or different accidents.
The proposed amendment does not adversely affect accident
initiators nor alter
[[Page 6649]]
design assumptions, conditions, or configurations of the facility.
The proposed amendment does not adversely affect the ability of SSCs
to perform their design function. The SSCs required to safely shut
down the reactor and maintain it in a safe shutdown condition remain
capable of performing their design functions.
The purpose of this amendment is to permit PTN to adopt a new
fire protection licensing basis which complies with the requirements
in 10 CFR 50.48(a) and (c) and the guidance of RG 1.205, Revision 1.
The NRC considers that NFPA 805 provides an acceptable methodology
and performance criteria for licensees to identify fire protection
systems and features that are an acceptable alternative to the 10
CFR Part 50, Appendix R fire protection features (69 FR 33536; June
16, 2004).
The requirements in NFPA 805 address only fire protection and
the impacts of fire on the plant that have already been evaluated.
Based on this, the implementation of this amendment does not create
the possibility of a new or different kind of accident from any kind
of accident previously evaluated. The proposed changes do not
involve new failure mechanisms or malfunctions that can initiate a
new accident.
Therefore, the possibility of a new or different kind of
accident from any kind of accident previously evaluated is not
created with the implementation of this amendment.
3. Does the proposed amendment involve a significant reduction
in the margin of safety?
Response: No.
Operation of PTN in accordance with the proposed amendment does
not involve a significant reduction in the margin of safety. The
proposed amendment does not alter the manner in which safety limits,
limiting safety system settings or limiting conditions for operation
are determined. The safety analysis acceptance criteria are not
affected by this change. The proposed amendment does not adversely
affect existing plant safety margins or the reliability of equipment
assumed to mitigate accidents in the UFSAR. The proposed amendment
does not adversely affect the ability of SSCs to perform their
design function. The SSCs required to safely shut down the reactor
and to maintain it in a safe shutdown condition remain capable of
performing their design function.
The purpose of this amendment is to permit PTN to adopt a new
fire protection licensing basis which complies with the requirements
in 10 CFR 50.48(a) and (c) and the guidance of RG 1.205, Revision 1.
The NRC considers that NFPA 805 provides an acceptable methodology
and performance criteria for licensees to identify fire protection
systems and features that are an acceptable alternative to the 10
CFR Part 50, Appendix R fire protection features (69 FR 33536; June
16, 2004). Engineering analyses, which may include engineering
evaluations, probabilistic safety assessments, and fire modeling
calculations, have been performed to demonstrate that the
performance-based methods do not result in a significant reduction
in the margin of safety.
Based on this, the implementation of this amendment does not
significantly reduce the margin of safety. The proposed changes are
evaluated to ensure that the risk and safety margins are kept within
acceptable limits.
Therefore, the transition does not involve a significant
reduction in the margin of safety.
The NFPA 805 continues to protect public health and safety and
the common defense and security because the overall approach of NFPA
805 is consistent with the key principles for evaluating license
basis changes, as described in RG 1.174, is consistent with the DID
philosophy, and maintains sufficient safety margins.
Margins previously established for the PTN program in accordance
with 10 CFR 50.48(b) and Appendix R to 10 CFR Part 50 are not
significantly reduced.
Therefore, this LAR does not result in a reduction in a margin
of safety.
The NRC staff 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: William S. Blair, Managing Attorney--
Nuclear, Florida Power & Light, 700 Universe Blvd., MS LAW/JB, Juno
Beach, Florida, 33408-0420.
NRC Branch Chief: Jessie F. Quichocho.
NextEra Energy Seabrook, LLC., Docket No. 50-443, Seabrook Station,
Unit 1, Rockingham County, New Hampshire
Date of amendment request: September 10, 2013. A publicly available
version is in ADAMS under Accession No. ML13260A160.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information (SUNSI). The proposed
amendment will modify the Seabrook Technical Specifications (TSs).
Specifically, the proposed amendment will revise TS 6.8.1.6.b, ``Core
Operating Limits Report,'' by adding Areva Licensing Report ANP-3243P,
``Seabrook Station, Unit 1 Fixed Incore Detector System Analysis
Supplement to YAEC-1855PA,'' dated July 31, 2013 (a publicly available
version is in ADAMS under Accession No. ML13260A161), which supplements
and modifies the previously approved methodology. The proposed change
also modifies the surveillance requirements associated with the heat
flux hot channel factor and nuclear enthalpy rise hot channel factor to
include revised uncertainty values when measurement is obtained using
the fixed incore detector system (FIDS).
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, along with the NRC's edits in
square brackets:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The FIDS is used for core surveillances to provide confirmatory
information on the neutron flux distribution of the core. This
system is not used for accident mitigation and does not provide any
automatic control functions or protective functions for the
operation of the plant.
As the proposed change does not involve any changes to the
physical equipment or operation of the system, there is no increase
in the probability of an accident previously evaluated.
The proposed Technical Specification (TS) change determines a
revised uncertainty value for the FQ [heat flux hot
channel factor] and F[Dgr]h [nuclear enthalpy rise hot
channel factor] TS surveillance parameters. ANP-3243P, ``Seabrook
Station Unit 1 Fixed Incore Detector System Analysis Supplement to
YAEC-1855PA,'' documents that these modifications yield results in
surveillance parameters that compare well to the original
methodology over the first 8 cycles. The report also documents that
the results of the uncertainty analysis using all 15 completed
cycles compared well to the results of the uncertainty analysis for
the original YAEC-1855PA methodology. The report concludes that the
revised FIDS analysis methodology remains comparable in accuracy and
functionality to the original YAEC-1855PA methodology and the
moveable incore detector system.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any previously evaluated?
Response: No.
The operation of the facility in accordance with the proposed
amendment does not create the possibility of a new or different kind
of accident from any accident previously evaluated since the
proposed change will not affect plant safety analysis assumptions or
the physical design of the facility. The revised uncertainty applied
to the measured core peaking factors ensures the safety limits are
maintained; hence, no new failure mode is introduced.
Therefore, the proposed changes do 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.
Margin of safety is associated with confidence in the ability of
the fission product barriers (i.e., fuel cladding, reactor coolant
system pressure boundary, and containment structure) to limit the
level of radiation dose to the public. The proposed
[[Page 6650]]
changes to modify the FIDS methodology and provide revised
uncertainty values for the FQ and F[Dgr]h TS
surveillance parameters do not involve a significant change in the
method of plant operation, and no accident analyses will be affected
by the proposed changes. Additionally, the proposed changes will not
relax any criteria used to establish safety limits and will not
relax any safety system settings. The safety analysis acceptance
criteria are not affected by this change. The proposed change will
not result in plant operation in a configuration outside the design
basis. The proposed change does not adversely affect systems that
respond to safely shutdown the plant and to maintain the plant in a
safe shutdown condition.
Therefore, the proposed changes do 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. James Petro, Managing Attorney, Florida
Power & Light Company, P.O. Box 14000, Juno Beach, Florida, 33408-0420.
Acting NRC Branch Chief: John G. Lamb.
Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation
Florida Power and Light Company, Docket Nos. 50-250 and 50-251, Turkey
Point Nuclear Generating, Units 3 and 4, Miami-Dade County, Florida;
NextEra Energy Seabrook, LLC., Docket No. 50-443, Seabrook Station,
Unit 1, Rockingham County, New Hampshire
A. This Order contains instructions regarding how potential parties
to this proceeding may request access to documents containing SUNSI.
B. Within 10 days after publication of this notice of hearing and
opportunity to petition for leave to intervene, any potential party who
believes access to SUNSI is necessary to respond to this notice may
request such access. A ``potential party'' is any person who intends to
participate as a party by demonstrating standing and filing an
admissible contention under 10 CFR 2.309. Requests for access to SUNSI
submitted later than 10 days after publication of this notice will not
be considered absent a showing of good cause for the late filing,
addressing why the request could not have been filed earlier.
C. The requestor shall submit a letter requesting permission to
access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, Attention: Rulemakings and
Adjudications Staff, and provide a copy to the Associate General
Counsel for Hearings, Enforcement and Administration, Office of the
General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001. The expedited delivery or courier mail address for both
offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike,
Rockville, Maryland 20852. The email address for the Office of the
Secretary and the Office of the General Counsel are
Hearing.Docket@nrc.gov and OGCmailcenter@nrc.gov, respectively.\1\ The
request must include the following information:
---------------------------------------------------------------------------
\1\ While a request for hearing or petition to intervene in this
proceeding must comply with the filing requirements of the NRC's
``E-Filing Rule,'' the initial request to access SUNSI under these
procedures should be submitted as described in this paragraph.
---------------------------------------------------------------------------
(1) A description of the licensing action with a citation to this
Federal Register notice;
(2) The name and address of the potential party and a description
of the potential party's particularized interest that could be harmed
by the action identified in C.(1); and
(3) The identity of the individual or entity requesting access to
SUNSI and the requestor's basis for the need for the information in
order to meaningfully participate in this adjudicatory proceeding. In
particular, the request must explain why publicly available versions of
the information requested would not be sufficient to provide the basis
and specificity for a proffered contention.
D. Based on an evaluation of the information submitted under
paragraph C.(3) the NRC staff will determine within 10 days of receipt
of the request whether:
(1) There is a reasonable basis to believe the petitioner is likely
to establish standing to participate in this NRC proceeding; and
(2) The requestor has established a legitimate need for access to
SUNSI.
E. If the NRC staff determines that the requestor satisfies both
D.(1) and D.(2) above, the NRC staff will notify the requestor in
writing that access to SUNSI has been granted. The written notification
will contain instructions on how the requestor may obtain copies of the
requested documents, and any other conditions that may apply to access
to those documents. These conditions may include, but are not limited
to, the signing of a Non-Disclosure Agreement or Affidavit, or
Protective Order \2\ setting forth terms and conditions to prevent the
unauthorized or inadvertent disclosure of SUNSI by each individual who
will be granted access to SUNSI.
---------------------------------------------------------------------------
\2\ Any motion for Protective Order or draft Non-Disclosure
Affidavit or Agreement for SUNSI must be filed with the presiding
officer or the Chief Administrative Judge if the presiding officer
has not yet been designated, within 30 days of the deadline for the
receipt of the written access request.
---------------------------------------------------------------------------
F. Filing of Contentions. Any contentions in these proceedings that
are based upon the information received as a result of the request made
for SUNSI must be filed by the requestor no later than 25 days after
the requestor is granted access to that information. However, if more
than 25 days remain between the date the petitioner is granted access
to the information and the deadline for filing all other contentions
(as established in the notice of hearing or opportunity for hearing),
the petitioner may file its SUNSI contentions by that later deadline.
This provision does not extend the time for filing a request for a
hearing and petition to intervene, which must comply with the
requirements of 10 CFR 2.309.
G. Review of Denials of Access.
(1) If the request for access to SUNSI is denied by the NRC staff
after a determination on standing and need for access, the NRC staff
shall immediately notify the requestor in writing, briefly stating the
reason or reasons for the denial.
(2) The requestor may challenge the NRC staff's adverse
determination by filing a challenge within 5 days of receipt of that
determination with: (a) The presiding officer designated in this
proceeding; (b) if no presiding officer has been appointed, the Chief
Administrative Judge, or if he or she is unavailable, another
administrative judge, or an administrative law judge with jurisdiction
pursuant to 10 CFR 2.318(a); or (c) if another officer has been
designated to rule on information access issues, with that officer.
H. Review of Grants of Access. A party other than the requestor may
challenge an NRC staff determination granting access to SUNSI whose
release would harm that party's interest independent of the proceeding.
Such a challenge must be filed with the Chief Administrative Judge
within 5 days of the notification by the NRC staff of its grant of
access.
If challenges to the NRC staff determinations are filed, these
procedures give way to the normal process for litigating disputes
concerning access to information. The availability of interlocutory
review by
[[Page 6651]]
the Commission of orders ruling on such NRC staff determinations
(whether granting or denying access) is governed by 10 CFR 2.311.\3\
---------------------------------------------------------------------------
\3\ Requestors should note that the filing requirements of the
NRC's E-Filing Rule (72 FR 49139; August 28, 2007) apply to appeals
of NRC staff determinations (because they must be served on a
presiding officer or the Commission, as applicable), but not to the
initial SUNSI request submitted to the NRC staff under these
procedures.
---------------------------------------------------------------------------
I. The Commission expects that the NRC staff and presiding officers
(and any other reviewing officers) will consider and resolve requests
for access to SUNSI, and motions for protective orders, in a timely
fashion in order to minimize any unnecessary delays in identifying
those petitioners who have standing and who have propounded contentions
meeting the specificity and basis requirements in 10 CFR Part 2.
Attachment 1 to this Order summarizes the general target schedule for
processing and resolving requests under these procedures.
It is so ordered.
Dated at Rockville, Maryland, this 22nd day of January 2014.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
ATTACHMENT 1--General Target Schedule for Processing and Resolving
Requests for Access to Sensitive Unclassified Non-Safeguards
Information in This Proceeding
------------------------------------------------------------------------
Day Event/activity
------------------------------------------------------------------------
0........................ Publication of Federal Register notice of
hearing and opportunity to petition for
leave to intervene, including order with
instructions for access requests.
10....................... Deadline for submitting requests for access
to Sensitive Unclassified Non-Safeguards
Information (SUNSI) with information:
supporting the standing of a potential party
identified by name and address; describing
the need for the information in order for
the potential party to participate
meaningfully in an adjudicatory proceeding.
60....................... Deadline for submitting petition for
intervention containing: (i) Demonstration
of standing; and (ii) all contentions whose
formulation does not require access to SUNSI
(+25 Answers to petition for intervention;
+7 petitioner/requestor reply).
20....................... Nuclear Regulatory Commission (NRC) staff
informs the requestor of the staff's
determination whether the request for access
provides a reasonable basis to believe
standing can be established and shows need
for SUNSI. (NRC staff also informs any party
to the proceeding whose interest independent
of the proceeding would be harmed by the
release of the information.) If NRC staff
makes the finding of need for SUNSI and
likelihood of standing, NRC staff begins
document processing (preparation of
redactions or review of redacted documents).
25....................... If NRC staff finds no ``need'' or no
likelihood of standing, the deadline for
requestor/petitioner to file a motion
seeking a ruling to reverse the NRC staff's
denial of access; NRC staff files copy of
access determination with the presiding
officer (or Chief Administrative Judge or
other designated officer, as appropriate).
If NRC staff finds ``need'' for SUNSI, the
deadline for any party to the proceeding
whose interest independent of the proceeding
would be harmed by the release of the
information to file a motion seeking a
ruling to reverse the NRC staff's grant of
access.
30....................... Deadline for NRC staff reply to motions to
reverse NRC staff determination(s).
40....................... (Receipt +30) If NRC staff finds standing and
need for SUNSI, deadline for NRC staff to
complete information processing and file
motion for Protective Order and draft Non-
Disclosure Affidavit. Deadline for applicant/
licensee to file Non-Disclosure Agreement
for SUNSI.
A........................ If access granted: Issuance of presiding
officer or other designated officer decision
on motion for protective order for access to
sensitive information (including schedule
for providing access and submission of
contentions) or decision reversing a final
adverse determination by the NRC staff.
A + 3.................... Deadline for filing executed Non-Disclosure
Affidavits. Access provided to SUNSI
consistent with decision issuing the
protective order.
A + 28................... Deadline for submission of contentions whose
development depends upon access to SUNSI.
However, if more than 25 days remain between
the petitioner's receipt of (or access to)
the information and the deadline for filing
all other contentions (as established in the
notice of hearing or opportunity for
hearing), the petitioner may file its SUNSI
contentions by that later deadline.
A + 53................... (Contention receipt +25) Answers to
contentions whose development depends upon
access to SUNSI.
A + 60................... (Answer receipt +7) Petitioner/Intervenor
reply to answers.
>A + 60.................. Decision on contention admission.
------------------------------------------------------------------------
[FR Doc. 2014-01597 Filed 2-3-14; 8:45 am]
BILLING CODE 7590-01-P