[Federal Register Volume 79, Number 13 (Tuesday, January 21, 2014)]
[Notices]
[Pages 3412-3420]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-00877]
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NUCLEAR REGULATORY COMMISSION
[NRC-2014-0010]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission 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 biweekly notice includes all notices of amendments issued, or
proposed to be issued from December 26, 2013 to January 8, 2014. The
last biweekly notice was published on January 7, 2014 (79 FR 855).
ADDRESSES: You may submit comments 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 http://www.regulations.gov and search for Docket ID NRC-2014-0010. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected].
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:
[[Page 3413]]
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2014-0010 when contacting the NRC
about the availability of information regarding this document. You may
access publicly-available information related to this document by any
of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0010.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number
for each document referenced in this document (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-2014-0010 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 you
comment submission. The NRC will post all comment submissions at http://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.
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 Sec. 50.92 of Title 10 of the Code of
Federal Regulations (10 CFR), this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Within 60 days after the date of publication of this notice, any
person(s) whose interest may be affected by this action may file a
request for a hearing and a petition to intervene with respect to
issuance of the amendment to the subject facility operating license or
combined license. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ``Agency
Rules of Practice and 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 regulations are accessible electronically from the NRC Library on
the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is
filed by the above date, the Commission or a presiding officer
designated by the Commission or by the Chief Administrative Judge of
the Atomic Safety and Licensing Board Panel, will rule on the request
and/or petition; and the Secretary or the Chief Administrative Judge of
the Atomic Safety and Licensing Board will issue a notice of a hearing
or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends
[[Page 3414]]
to rely to establish those facts or expert opinion. The petition must
include sufficient information to show that a genuine dispute exists
with the applicant on a material issue of law or fact. Contentions
shall be limited to matters within the scope of the amendment under
consideration. The contention must be one which, if proven, would
entitle the requestor/petitioner to relief. A requestor/petitioner who
fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in the NRC adjudicatory proceedings, including
a request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139;
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at http://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with the NRC guidance
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC's Web site
at http://www.nrc.gov/site-help/e-submittals.html, by email to
[email protected], or by a toll-free call at 1-866 672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852, Attention: Rulemaking and Adjudications Staff. Participants
filing a document in this manner are responsible for serving the
document on all other participants. Filing is considered complete by
first-class mail as of the time of deposit in the mail, or by courier,
express mail, or expedited delivery service upon depositing the
document with the provider of the service. A presiding officer, having
granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's
[[Page 3415]]
electronic hearing docket which is available to the public at http://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 license amendment
application, see the application for amendment which is available for
public inspection at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC's PDR Reference staff at 1-800-397-4209,
301-415-4737, or by email to [email protected].
Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire
Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina
Date of amendment request: October 28, 2013. A publicly available
version is available in ADAMS under Accession No. ML13304B445.
Description of amendment request: This amendment request contains
sensitive unclassified non-safeguards information. The amendments
request for a one-time change to Technical Specification 3.8.4, ``DC
Sources-Operating'' for battery replacement.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
Removing one vital battery from service for a limited period of
time does not involve a significant increase in the probability or
consequences of an accident.
All four vital batteries have been sized to carry the load duty
cycle for their respective bus/train while maintaining battery
terminal voltage in a cross-tied alignment during a LOOP with a DBE
on one unit and safe shut down of the other unit. The vital battery
cross-tie alignment is part of the McGuire licensing basis, is in
the Technical Specifications, and is routinely performed.
In addition, for defense-in-depth and risk mitigation measures,
a fully sized temporary battery will be available as a defense in
depth, back-up DC power supply for plant recovery and accident
mitigation.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
Operation in accordance with the proposed LAR does not create a
new plant configuration, nor adversely affect how the plant is
currently operated. During the time period of each vital battery
bank replacement, the associated DC channel will remain energized by
being cross-tied to another operable DC channel as designed and as
allowed by TS 3.8.4. This is a normal plant alignment, it maintains
train independence, and is performed numerous times during a fuel
cycle for vital battery maintenance and surveillance testing. No new
accident causal mechanisms are created as a result of this proposed
LAR. No changes are being made to any structure, system, or
component which will introduce any new accident causal mechanisms.
The temporary battery remains physically and electrically isolated
from the rest of the 125VDC system via an open disconnect switch.
The cable between the spare charger and the disconnect will remain
de-energized by isolation from the charger's DC output breaker and
both crosstie breakers. This proposed LAR does not impact any plant
systems that are accident initiators and does not impact any safety
analysis.
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 amendment involve a significant reduction
in the margin of safety?
Response: No.
The proposed LAR does not physically alter the present plant
design nor affect how the plant is currently operated. This activity
only extends the amount of time that vital DC channels are allowed
to be cross-tied. So a significant reduction in the margin of safety
does not occur.
Margin of safety is related to the confidence in the ability of
the fission product barriers to perform their design functions
during and following an accident situation. These barriers include
the fuel cladding, the reactor coolant system, and the containment
system. The performance of the fuel cladding, reactor coolant and
containment systems will not be impacted by the proposed LAR.
Therefore, it is concluded that the proposed changes do not
involve a significant reduction in the margin of safety.
Based upon the above evaluation, Duke Energy concludes that the
proposed amendment presents no significant hazards consideration
under the standards set forth in 10 CFR 50.92(c) and, accordingly, a
finding of ``no significant hazards consideration'' is justified.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Lara S. Nichols, Associate General Counsel,
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC
28202.
NRC Branch Chief: Robert J. Pascarelli.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: October 2, 2013.
Description of amendment request: The proposed amendment
incorporates Technical Specification Task Force (TSTF) Traveler TSTF-
493-A, Revision 4, ``Clarify Application of Setpoint Methodology for
LSSS [limiting safety system settings] Functions,'' Option A. The
availability of this Technical Specification (TS) improvement was
announced in the Federal Register on May 11, 2010 (75 FR 26294). The
proposed amendment would revise the TSs by adding requirements to
assess channel performance during testing that verifies instrument
channel setting values established by plant-specific setpoint
methodologies to all the functions identified in TSTF-493, Revision 4,
Appendix A.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the
[[Page 3416]]
issue of no significant hazards consideration, which is presented
below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change adds test requirements to TS instrument
Functions related to those variables that have a significant safety
function to ensure that instruments will function as required to
initiate protective systems or actuate mitigating systems at the
point assumed in the applicable safety analysis.
Surveillance tests are not an initiator to any accident
previously evaluated. As a result, the probability of any accident
previously evaluated is not significantly increased. The systems and
components required by the TS for which surveillance Notes are added
are still required to be operable, meet the acceptance criteria for
the surveillance requirements, and be capable of performing any
mitigation function assumed in the accident analysis.
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 accident previously evaluated?
Response: No.
The change does not involve a physical alteration of the plant,
i.e., no new or different type of equipment will be installed. The
change does not alter assumptions made in the safety analysis but
ensures that the instruments perform as assumed in the accident
analysis. The proposed change is consistent with the safety analysis
assumptions. Therefore, the proposed change does not create the
possibility of a new or different kind of accident from any
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change adds test requirements that will assure that
TS instrumentation AVs [allowable values] (1) will be limiting
settings for assessing instrument channel operability and (2) will
be conservatively determined so that evaluation of instrument
performance history and the ALT [as-left tolerance] requirements of
the calibration procedures will not have an adverse effect on
equipment operability. The testing methods and acceptance criteria
for systems, structures, and components specified in applicable
codes and standards (or alternatives approved for use by the NRC)
will continue to be met as described in the plant licensing basis
including the updated FSAR [final safety analysis report]. There is
no impact to safety analysis acceptance criteria as described in the
plant licensing basis because no change is made to the accident
analysis assumptions.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: William A. Horin, Esq., Winston & Strawn,
1700 K Street NW., Washington, DC 20006-3817.
NRC Branch Chief: Michael T. Markley.
FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and
50-412, Beaver Valley Power Station, Units 1 and 2, Beaver County,
Pennsylvania
Date of amendment request: October 18, 2013.
Description of amendment request: The amendment would change the
Beaver Valley Power Station Technical Specifications (TS).
Specifically, this change request involves the adoption of an approved
change to the standard TS for Westinghouse plants (NUREG-1431), to
allow relocation of specific TS surveillance frequencies to a licensee-
controlled program. The proposed change is described in TS Task Force
(TSTF) Traveler, TSTF-425, Revision 3, ``Relocation Surveillance
Frequencies to Licensee Control--RITSTF Initiative 5b'' (ADAMS
Accession No. ML090850642). A Notice of Availability was published in
the Federal Register on July 6, 2009 (74 FR 31996).
The proposed change relocates surveillance frequencies to a
licensee-controlled program, the Surveillance Frequency Control
Program. This change is applicable to licensees using probabilistic
risk guidelines contained in NRC-approved NEI 04-10, Revision 1,
``Risk-Informed Technical Specifications Initiative 5b, Risk-Informed
Method for Control of Surveillance Frequencies'' (ADAMS Accession No.
ML071360456).
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 NRC edits in square
brackets:
1. Do the proposed changes involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
The proposed change relocates the specified frequencies for
periodic surveillance requirements to licensee control under a new
Surveillance Frequency Control Program. Surveillance frequencies are
not an initiator to any accident previously evaluated. As a result,
the probability of any accident previously evaluated is not
significantly increased. The systems and components required by the
technical specifications for which the surveillance frequencies are
relocated are still required to be operable, meet the acceptance
criteria for the surveillance requirements, and be capable of
performing any mitigation function assumed in the accident analysis.
As a result, the consequences of any accident previously evaluated
are not significantly increased.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Do the proposed changes create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
No new or different accidents result from utilizing the proposed
change. The changes do not involve a physical alteration of the
plant (that is, no new or different type of equipment will be
installed) or a change in the methods governing normal plant
operation. In addition, the changes do not impose any new or
different requirements. The changes do not alter assumptions made in
the safety analysis. The proposed changes are consistent with the
safety analysis assumptions and current plant operating practice.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Do the proposed changes involve a significant reduction in a
margin of safety?
Response: No.
The design, operation, testing methods, and acceptance criteria
for systems, structures, and components (SSCs), specified in
applicable codes and standards (or alternatives approved for use by
the NRC) will continue to be met as described in the plant licensing
basis (including the final safety analysis report and bases to the
TS), since these are not affected by changes to the surveillance
frequencies. Similarly, there is no impact to safety analysis
acceptance criteria as described in the plant licensing basis.
To evaluate a change in the relocated surveillance frequency,
[FirstEnergy Nuclear Operating Co.] FENOC will perform a
probabilistic risk evaluation using the guidance contained in NRC
approved Nuclear Energy Instituted (NEI) 04-10, Revision 1, in
accordance with the TS Surveillance Frequency Control Program. NEI
04-10, Revision 1, methodology provides reasonable acceptance
guidelines and methods for evaluating the risk increase of proposed
changes to surveillance frequencies consistent with Regulatory Guide
1.177, ``An Approach for Plant-Specific, Risk Informed
Decisionmaking: Technical Specifications.''
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
[[Page 3417]]
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David W. Jenkins, FirstEnergy Nuclear
Operating Company, FirstEnergy Corporation, 76 South Main Street,
Akron, OH 44308.
Acting NRC Branch Chief: John G. Lamb.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station,
Unit 1, Washington County, Nebraska
Date of amendment request: February 18, 2013.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) Definitions and TS Sections 2.0.1
and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable
Power Source. Specifically, the proposed amendment would: (1) Revise
the definition for Operable--Operability in the Fort Calhoun Station
TS; (2) modify the provisions under which equipment may be considered
operable when either its normal or emergency power source is
inoperable; and (3) revise the minimum requirement statement in TS 2.7
to the wording previously reviewed and approved by the NRC in Amendment
No. 147 dated August 2, 1992.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to revise the definition of operable-
operability, modify the provisions under which equipment may be
considered operable when either its normal or emergency power source
is inoperable, add Technical Specification (TS) limiting conditions
for operation (LCO) 2.0.1(2), and relocate the guidance for
inoperable power supplies and verifying operability of redundant
components into the LCO for electrical equipment is more aligned
with NUREG-0212, Revision 2, Standard Technical Specifications [STS]
for Combustion Engineering Plants, and does not adversely impact the
probability of an accident previously evaluated. The proposed change
does not affect the operability requirements for the emergency
diesel generators (DGs) or the house service transformers, and
therefore does not impact the consequences of an analyzed accident.
In addition, the administrative changes to renumber the existing TS
sections ``TS 2.0.1(2) to 2.0.1(3)'' is being made as a result of
additions to previous TS paragraphs and are being made for
consistency and clarification. Also, revising the minimum
requirement statement in TS 2.7 to the wording previously reviewed
and approved by the NRC in Amendment 147 is an administrative change
as the wording reverted to its pre-Amendment 147. This wording
simply corrects previous administrative errors when TS Amendment 162
was issued on March 29, 1994.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes do not involve a physical alteration to the
plant (i.e., no new or different type of equipment will be
installed) or a change in methods governing normal plant operation.
The proposed changes to TS 2.0.1(2) and TS 2.7 do not create the
possibility of a new or different kind of accident since the design
function of the affected equipment is not changed. No new
interactions between systems or components are created. No new
failure mechanisms of associated systems will exist.
No new failure mechanisms would be created. The proposed changes
do not alter any assumptions made in the safety analyses.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes to add TS 2.0.1(2) and relocate the
guidance for inoperable power supplies and verifying operability of
redundant components from TS LCO 2.7 do not alter the manner in
which safety limits or limiting safety system settings are
determined. The safety analysis acceptance criteria are not affected
by these proposed changes. The sources of power credited for design
basis events are not affected by the proposed changes.
The proposed changes to modify the provisions under which
equipment may be considered operable when either its normal or
emergency power source is inoperable, and relocate the guidance for
inoperable power supplies and verifying operability of redundant
components into the
TS 2.0.1 LCO is more aligned with the STS contained in NUREG-
0212.
Further, the proposed change does not change the design function
of any equipment assumed to operate in the event of an accident.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David A. Repka, Esq., Winston & Strawn, 1700
K Street NW., Washington, DC 20006-3817.
NRC Branch Chief: Michael T. Markley.
Southern Nuclear Operating Company, Inc. Docket Nos. 52-025 and 52-026,
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia
Date of amendment request: November 27, 2013.
Description of amendment request: The requested amendment
reclassifies portions of the five Tier 2* Human Factors (HF)
Verification & Validation (V&V) planning documents listed in the
Updated Final Safety Analysis Report (UFSAR) Table 1.6-1 and Chapter
18, Subsection 18.11.2. These five documents outline the overall plan
for the HF V&V, including the Human Factors Engineering (HFE) design
verification, task support verification, integrated system validation,
discrepancy resolution process, and verification at plant startup. The
licensee stated that the requested amendment identifies the portions of
the five HF V&V planning documents that would more appropriately be
classified as Tier 2, due to those portions having no impact on safety,
and proposes the necessary departures to reclassify this information.
This differentiation between Tier 2 and Tier 2* information in the HF
V&V planning documents will allow for revisions of these documents
using the Tier 2 change process provided in 10 CFR Part 52, Appendix D,
Section VIII.B.5.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes reclassify portions of the five Tier 2*
Human Factors (HF) Verification & Validation (V&V) planning
documents listed in the Updated Final Safety Analysis Report
(UFSAR). These changes do not modify the design, construction, or
operation of any plant structures, systems, or components (SSC), nor
do they change any procedures or method of control for any SSCs.
Because the proposed changes do not change the design, construction,
or operation of any SSCs, they do not adversely affect any
[[Page 3418]]
design function as described in the UFSAR. Therefore, the proposed
amendment does not affect the probability of an accident previously
evaluated. Similarly, because the proposed changes do not alter the
design or operation of the nuclear plant or any plant SSCs, the
proposed changes do not represent a change to the radiological
effects of an accident, and therefore, they do not involve an
increase in the consequences of an accident previously evaluated.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes are not a modification, addition to, or
removal of any plant SSCs. Furthermore, the proposed changes are not
a change to procedures or method of control of the nuclear plant or
any plant SSCs. The only impact of this activity is the
reclassification of portions of the five HF V&V planning documents
as Tier 2 information. Because the proposed amendment does not
change the design, construction, or operation of the nuclear plant
or any plant operations, it does not affect the possibility of an
accident.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes reclassify portions of the five Tier 2* HF
V&V planning documents listed in the UFSAR from Tier 2* to Tier 2.
The proposed amendment only affects the classification of planning
documents and does not change the design, construction, or operation
of the nuclear plant or any plant operations; therefore, the changes
do not affect any margin of safety.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. M. Stanford Blanton, Blach & Bingham
LLP, 1710 Sixth Avenue North, Birmingham, AL 35203-2015.
NRC Branch Chief: Lawrence J. Burkhart.
Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of amendment request: September 26, 2013.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) Surveillance Requirement (SR)
3.7.10.1 and SR 3.7.13.1 to reduce the required run time for periodic
operation of the control room pressurization system filter trains and
emergency exhaust system filter trains, with heaters on, from 10 hours
to 15 minutes, consistent with Technical Specifications Task Force
(TSTF) change traveler TSTF-522-A, Revision 0, ``Revise Ventilation
System Surveillance Requirements to Operate for 10 hours per Month,''
with minor variations. The Notice of Availability and model safety
evaluation of the TS improvement were published in the Federal Register
on September 20, 2012 (77 FR 58421).
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change replaces existing Surveillance Requirements
to operate the Control Room Emergency Ventilation System (CREVS) and
the Emergency Exhaust System (EES) for a continuous 10-hour period
with applicable heaters operating at a frequency controlled in
accordance with the SFCP [Surveillance Frequency Control Program],
with requirements to operate these systems for 15 continuous minutes
with applicable heaters operating at a frequency controlled in
accordance with the SFCP.
These systems are not accident initiators (i.e., their
malfunction cannot initiate an accident or transient) and therefore,
these changes do not involve a significant increase in the
probability of an accident. The proposed system and filter testing
changes are consistent with current regulatory guidance for these
systems and will continue to assure that these systems perform their
design function which may include mitigating accidents. Therefore,
the change does not involve a significant increase in the
consequences of an accident.
Therefore, it is concluded that this 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 accident previously evaluated?
Response: No.
The change proposed for these ventilation systems does not
change any system operations or maintenance activities. Testing
requirements will be revised and will continue to demonstrate that
the Limiting Conditions for Operation are met and the system
components are capable of performing their intended safety
functions. The change does not create new failure modes or
mechanisms and no new accident precursors are generated.
Therefore, it is concluded that this change does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The design basis for the ventilation system heaters in the EES
and in the pressurization trains of the CREVS includes the
capability to heat the incoming air, reducing the relative humidity
(and thereby increasing adsorber efficiency). The heater testing
change proposed will continue to demonstrate that the heaters are
capable of heating the air and will thus perform their design
function. The proposed change is consistent with regulatory
guidance.
Therefore, it is concluded that this change does not involve a
significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: John O'Neill, Esq., Pillsbury Winthrop Shaw
Pittman LLP, 2300 N Street NW., Washington, DC 20037.
NRC Branch Chief: Michael T. Markley.
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental
[[Page 3419]]
impact statement or environmental assessment need be prepared for these
amendments. If the Commission has prepared an environmental assessment
under the special circumstances provision in 10 CFR 51.22(b) and has
made a determination based on that assessment, it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection at
the NRC's Public Document Room (PDR), located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by email to
[email protected].
Entergy Operations, Inc., System Energy Resources, Inc., South
Mississippi Electric Power Association, and Entergy Mississippi, Inc.,
Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne
County, Mississippi
Date of application for amendment: October 2, 2012, as supplemented
by letters dated April 26, June 4, August 15, September 24, September
26, October 14, November 12, December 5, and December 11, 2013.
Brief description of amendment: The amendment revised the Technical
Specifications (TS) for the Grand Gulf Nuclear Station, Unit 1 (GGNS)
to support operation with 24-month fuel cycles. Specifically, the
change revised the frequency of certain TS Surveillance Requirements
(SRs) from ``18 months'' to ``24 months,'' in accordance with the
guidance of NRC's Generic Letter (GL) 91-04, ``Changes in Technical
Specification Surveillance Intervals to Accommodate a 24-Month Fuel
Cycle,'' dated April 2, 1991. Consistent with the GL, changes were also
made to the Administrative Controls TS Section 5.5.7, ``Ventilation
Filter Testing Program (VFTP),'' to address changes to 18-month
frequencies that are specified in NRC Regulatory Guide (RG) 1.52,
Revision 2, ``Design, Testing, and Maintenance Criteria for Post-
Accident Engineered-Safety-Feature Atmosphere Cleanup System Air
Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power
Plants,'' March 1978, to 24-month frequencies. By letter dated December
11, 2013, the licensee withdrew its April 26, 2013, request to modify
SR 3.7.7.2 in TS 3.7.7, ``Main Turbine Bypass System.'' Therefore, the
NRC staff neither evaluated a change to, nor changed, the surveillance
interval of SR 3.7.7.2.
Date of issuance: December 26, 2013.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No: 197.
Facility Operating License No. NPF-29: The amendment revised the
Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: November 13, 2012 (77
FR 67681). The supplemental letters dated April 26, June 4, August 15,
September 24, September 26, October 14, November 12, December 5, and
December 11, 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 December 26, 2013.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota (NSPM), Docket No. 50-263,
Monticello Nuclear Generating Plant (MNGP), Wright County, Minnesota
Date of application for amendment: December 11, 2008, as
supplemented by letters dated, May 20, 2008, May 28, 2008, May 30,
2008, June 3, 2008, June 5, 2008, June 12, 2008, June 25, 2008,
December 11, 2008, January 29, 2009, February 4, 2009 (2 letters),
February 17, 2009, February 24, 2009, March 19, 2009, April 22, 2009,
May 13, 2009, May 26, 2009, May 28, 2009, May 29, 2009, June 12, 2009,
June 16, 2009, July 13, 2009, July 23, 2009, August 12, 2009 (2
letters), August 19, 2009, August 21, 2009 (2 letters), August 26,
2009, August 31, 2009, October 1, 2009, January 25, 2010, April 6,
2010, December 21, 2010, June 30, 2010, April 5, 2011, July 7, 2011,
August 30, 2011, November 11, 2011, January 13, 2012, July 19, 2012,
July 19, 2012, September 28, 2012, October 21, 2012, October 22, 2012,
October 30, 2012, November 30, 2012, January 21, 2013, January 31,
2013, February 22, 2013, February 27, 2013, March 7, 2013, March 18,
2013, March 21, 2013, March 29, 2013, April 10, 2013, May 13, 2013, May
30, 2013, June 26, 2013, July 8, 2013, July 18, 2013 (2 letters),
August 2, 2013, September 30, 2013, and November 8, 2013.
Brief description of amendment: The amendment increased the
authorized maximum licensed thermal power level from the current
licensed thermal power of 1,775 megawatts thermal (MWt) to 2,004 MWt,
which is an increase of approximately 13 percent. The proposed increase
in power level is considered an extended power uprate.
Date of issuance: December 9, 2013.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No: 176.
Renewed Facility Operating License No. DPR-22: The amendment
revised the Renewed Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: January 23, 2009 (74 FR
4252). The supplemental letters dated May 20, 2008, May 28, 2008, May
30, 2008, June 3, 2008, June 5, 2008, June 12, 2008, June 25, 2008,
December 11, 2008, January 29, 2009, February 4, 2009 (2 letters),
February 17, 2009, February 24, 2009, March 19, 2009, April 22, 2009,
May 13, 2009, May 26, 2009, May 28, 2009, May 29, 2009, June 12, 2009,
June 16, 2009, July 13, 2009, July 23, 2009, August 12, 2009 (2
letters), August 19, 2009, August 21, 2009 (2 letters), August 26,
2009, August 31, 2009, October 1, 2009, January 25, 2010, April 6,
2010, December 21, 2010, June 30, 2010, April 5, 2011, July 7, 2011,
August 30, 2011, November 11, 2011, January 13, 2012, July 19, 2012,
July 19, 2012, September 28, 2012, October 21, 2012, October 22, 2012,
October 30, 2012, November 30, 2012, January 21, 2013, January 31,
2013, February 22, 2013, February 27, 2013, March 7, 2013, March 18,
2013, March 21, 2013, March 29, 2013, April 10, 2013, May 13, 2013, May
30, 2013, June 26, 2013, July 8, 2013, July 18, 2013 (2 letters),
August 2, 2013, September 30, 2013, and November 8, 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 December 9, 2013.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 10th day of January 2014.
[[Page 3420]]
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2014-00877 Filed 1-17-14; 8:45 am]
BILLING CODE 7590-01-P