Biweekly Notice of Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 20070-20077 [2012-7676]
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20070
Federal Register / Vol. 77, No. 64 / Tuesday, April 3, 2012 / Notices
TABLE 2—SUMMARY OF RADIOLOGICAL ENVIRONMENTAL IMPACTS—Continued
Radioactive Solid Waste ...........................
Spent Nuclear Fuel ...................................
Postulated Design-Basis Accident Doses
Cumulative Radiological ...........................
Amount of additional radioactive solid waste generated would be handled by the existing system.
The spent fuel characteristics will remain within the bounding criteria used in the impact analysis in
10 CFR Part 51, Table S–3 and Table S–4.
Calculated doses for postulated design-basis accidents would remain within NRC limits.
Radiation doses to the public and plant workers would remain below NRC and EPA radiation protection standards.
Alternatives to the Proposed Action
As an alternative to the proposed
action, the NRC staff considered denial
of the proposed EPU (i.e., the ‘‘noaction’’ alternative). Denial of the
application would result in no change
in the current environmental impacts.
However, if the EPU were not approved
for PTN Units 3 and 4, other agencies
and electric power organizations may be
required to pursue other means, such as
fossil fuel or alternative fuel power
generation, to provide electric
generation capacity to offset future
demand. Construction and operation of
such a fossil-fueled or alternative-fueled
plant could result in impacts in air
quality, land use, and waste
management greater than those
identified for the proposed EPU for PTN
Units 3 and 4. Furthermore, the
proposed EPU does not involve
environmental impacts that are
significantly different from those
originally identified in the PTN Unit 3
or Unit 4 FES, and NUREG–1437, SEIS–
5.
Alternative Use of Resources
The action does not involve the use of
any different resources than those
previously considered in the PTN Unit
3 or Unit 4 FES.
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Agencies and Persons Consulted
In accordance with its stated policy,
the NRC staff consulted with the FDEP,
SFWMD, Miami-Dade County, BNP, and
FWCC regarding the environmental
impact of the proposed action and
specifically regarding the monitoring
and mitigation plan that formed the
basis of the Florida agencies
recommending approval to the FDEP for
the proposed EPU subject to the CoC
during the State of Florida site
certification process.
III. Finding of No Significant Impact
On the basis of the details provided in
the EA, the NRC concludes that granting
the proposed EPU license amendment is
not expected to cause impacts
significantly greater than current
operations. Therefore, the proposed
action of implementing the EPU for PTN
Units 3 and 4 will not have a significant
effect on the quality of the human
environment because no significant
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permanent changes are involved and the
temporary impacts are within
previously disturbed areas at the site
and the capacity of the plant systems.
Accordingly, the NRC has determined it
is not necessary to prepare an
environmental impact statement for the
proposed action.
Dated at Rockville, Maryland, this 27th day
of March 2012.
For the Nuclear Regulatory Commission.
Jason C. Paige,
Project Manager, Plant Licensing Branch 2–
2, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. 2012–7947 Filed 4–2–12; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0078]
Biweekly Notice of 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 (the Commission or NRC)
is publishing this regular biweekly
notice. The Act requires the
Commission publish notice of any
amendments issued, or proposed to be
issued and grants the Commission the
authority to issue and make
immediately effective any amendment
to an operating license 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 March 8,
2012, to March 21, 2012. The last
biweekly notice was published on
March 20, 2012 (77 FR 16271).
ADDRESSES: You may access information
and comment submissions related to
this document, which the NRC
possesses and is publicly available, by
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searching on https://www.regulations.gov
under Docket ID 2012–0078.
You may submit comments by the
following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID 2012–0078. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–492–3668;
email: Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: TWB–05–
B01M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
• Fax comments to: RADB at 301–
492–3446.
For additional direction on accessing
information and submitting comments,
see ‘‘Accessing Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and
Submitting Comments
A. Accessing Information
Please refer to Docket ID 2012–0078
when contacting the NRC about the
availability of information regarding this
document. You may access information
related to this document, which the
NRC possesses and is publicly available,
by the following methods:
• Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for Docket ID 2012–0078.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
select ‘‘ADAMS Public Documents’’ and
then select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov.
Documents may be viewed in ADAMS
by performing a search on the document
date and docket number.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
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White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
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B. Submitting Comments
Please include Docket ID 2012–0078
in the subject line of your comment
submission, in order to ensure that the
NRC is able to make your comment
submission available to the public in
this docket.
The NRC cautions you not to include
identifying or contact information in
comment submissions that you do not
want to be publicly disclosed. The NRC
posts all comment submissions at
https://www.regulations.gov as well as
entering the comment submissions into
ADAMS, and the NRC does not edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information in
their comment submissions that they do
not want to be publicly disclosed. Your
request should state that the NRC will
not edit comment submissions to
remove such information before making
the comment submissions available to
the public or entering the comment
submissions into ADAMS.
Notice of Consideration of Issuance of
Amendments to Facility Operating
Licenses 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
Title 10 of the Code of Federal
Regulations (10 CFR) 50.92, this means
that operation of the facility in
accordance with the proposed
amendment would not (1) involve a
significant increase in the probability or
consequences of an accident previously
evaluated; 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
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publication of this notice. The
Commission may issue the license
amendment before expiration of the 60day period provided that its final
determination is that the amendment
involves no significant hazards
consideration. In addition, the
Commission may issue the amendment
prior to the expiration of the 30-day
comment period should circumstances
change during the 30-day comment
period such that failure to act in a
timely way would result, for example in
derating or shutdown of the facility.
Should the Commission take action
prior to the expiration of either the
comment period or the notice period, it
will publish in the Federal Register a
notice of issuance. Should the
Commission make a final No Significant
Hazards Consideration Determination,
any hearing will take place after
issuance. The Commission expects that
the need to take this action will occur
very infrequently.
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 ‘‘Rules of
Practice for Domestic Licensing
Proceedings’’ in 10 CFR Part 2.
Interested person(s) should consult a
current copy of 10 CFR 2.309, which is
available at the NRC’s PDR, located at
One White Flint North, Room O1–F21,
11555 Rockville Pike (first floor),
Rockville, Maryland 20852. The NRC
regulations are accessible electronically
from the NRC Library on the NRC’s Web
site at https://www.nrc.gov/reading-rm/
doc-collections/cfr/. If a request for a
hearing or petition for leave to intervene
is filed by the above date, the
Commission or a presiding officer
designated by the Commission or by the
Chief Administrative Judge of the
Atomic Safety and Licensing Board
Panel, will rule on the request and/or
petition; and the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner in the proceeding, and
how that interest may be affected by the
results of the proceeding. The petition
should specifically explain the reasons
why intervention should be permitted
with particular reference to the
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following general requirements: (1) The
name, address, and telephone number of
the requestor or petitioner; (2) the
nature of the requestor’s/petitioner’s
right under the Act to be made a party
to the proceeding; (3) the nature and
extent of the requestor’s/petitioner’s
property, financial, or other interest in
the proceeding; and (4) the possible
effect of any decision or order which
may be entered in the proceeding on the
requestor’s/petitioner’s interest. The
petition must also identify the specific
contentions which the requestor/
petitioner seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the requestor/petitioner shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the requestor/petitioner
intends to rely in proving the contention
at the hearing. The requestor/petitioner
must also provide references to those
specific sources and documents of
which the petitioner is aware and on
which the requestor/petitioner intends
to rely to establish those facts or expert
opinion. The petition must include
sufficient information to show that a
genuine dispute exists with the
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
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would take place before the issuance of
any amendment.
All documents filed in NRC
adjudicatory proceedings, including a
request for hearing, a petition for leave
to intervene, any motion or other
document filed in the proceeding prior
to the submission of a request for
hearing or petition to intervene, and
documents filed by interested
governmental entities participating
under 10 CFR 2.315(c), must be filed in
accordance with the NRC 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 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 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/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
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participant must file the document
using the NRC’s online, Web-based
submission form. In order to serve
documents through the Electronic
Information Exchange System, users
will be required to install a Web
browser plug-in from the NRC’s Web
site. Further information on the Webbased submission form, including the
installation of the Web browser plug-in,
is available on the NRC’s public Web
site at https://www.nrc.gov/site-help/esubmittals.html.
Once a participant has obtained a
digital ID certificate and a docket has
been created, the participant can then
submit a request for hearing or petition
for leave to intervene. Submissions
should be in Portable Document Format
(PDF) in accordance with the NRC
guidance available on the NRC’s public
Web site at https://www.nrc.gov/sitehelp/e-submittals.html. A filing is
considered complete at the time the
documents are submitted through the
NRC’s E–Filing system. To be timely, an
electronic filing must be submitted to
the E–Filing system no later than 11:59
p.m. Eastern Time on the due date.
Upon receipt of a transmission, the E–
Filing system time-stamps the document
and sends the submitter an email notice
confirming receipt of the document. The
E–Filing system also distributes an
email notice that provides access to the
document to the NRC’s Office of the
General Counsel and any others who
have advised the Office of the Secretary
that they wish to participate in the
proceeding, so that the filer need not
serve the documents on those
participants separately. Therefore,
applicants and other participants (or
their counsel or representative) must
apply for and receive a digital ID
certificate before a hearing request/
petition to intervene is filed so that they
can obtain access to the document via
the E–Filing system.
A person filing electronically using
the agency’s adjudicatory E–Filing
system may seek assistance by
contacting the NRC Meta System Help
Desk through the ‘‘Contact Us’’ link
located on the NRC Web site at https://
www.nrc.gov/site-help/esubmittals.html, by email at
MSHD.Resource@nrc.gov, or by a tollfree call at 1–866 672–7640. The NRC
Meta System Help Desk is available
between 8 a.m. and 8 p.m., Eastern
Time, Monday through Friday,
excluding government holidays.
Participants who believe that they
have a good cause for not submitting
documents electronically must file an
exemption request, in accordance with
10 CFR 2.302(g), with their initial paper
filing requesting authorization to
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continue to submit documents in paper
format. Such filings must be submitted
by: (1) First class mail addressed to the
Office of the Secretary of the
Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
Adjudications Staff; or (2) courier,
express mail, or expedited delivery
service to the Office of the Secretary,
Sixteenth Floor, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852, Attention: Rulemaking
and Adjudications Staff. Participants
filing a document in this manner are
responsible for serving the document on
all other participants. Filing is
considered complete by first-class mail
as of the time of deposit in the mail, or
by courier, express mail, or expedited
delivery service upon depositing the
document with the provider of the
service. A presiding officer, having
granted an exemption request from
using E–Filing, may require a
participant or party to use E–Filing if
the presiding officer subsequently
determines that the reason for granting
the exemption from use of E–Filing no
longer exists.
Documents submitted in adjudicatory
proceedings will appear in the NRC’s
electronic hearing docket which is
available to the public at https://
ehd1.nrc.gov/ehd/, unless excluded
pursuant to an order of the Commission,
or the presiding officer. Participants are
requested not to include personal
privacy information, such as social
security numbers, home addresses, or
home phone numbers in their filings,
unless an NRC regulation or other law
requires submission of such
information. With respect to
copyrighted works, except for limited
excerpts that serve the purpose of the
adjudicatory filings and would
constitute a Fair Use application,
participants are requested not to include
copyrighted materials in their
submission.
Petitions for leave to intervene must
be filed no later than 60 days from the
date of publication of this notice. Nontimely filings will not be entertained
absent a determination by the presiding
officer that the petition or request
should be granted or the contentions
should be admitted, based on a
balancing of the factors specified in 10
CFR 2.309(c)(1)(i)–(viii).
For further details with respect to this
license amendment application, see the
application for amendment which is
available for public inspection at the
NRC’s PDR, located at One White Flint
North, Room O1–F21, 11555 Rockville
Pike (first floor), Rockville, Maryland
20852. Publicly available documents
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created or received at the NRC are
accessible electronically through
ADAMS in the NRC Library at https://
www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to
ADAMS or who encounter problems in
accessing the documents located in
ADAMS, should contact the NRC’s PDR
Reference staff at 1–800–397–4209, 301–
415–4737, or by email to
pdr.resource@nrc.gov.
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Detroit Edison, Docket No. 50–341,
Fermi 2, Monroe County, Michigan
Date of amendment request:
December 20, 2011.
Description of amendment request:
The proposed amendment would
modify Technical Specifications
requirements related to primary
containment isolation instrumentation.
The changes are in accordance with
Nuclear Regulatory Commission
approved Technical Specification Task
Force (TSTF), Improved Standard
Technical Specifications change TSTF–
306, Revision 2.
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 addition of the note that the
penetration flow path may be unisolated
under administrative control provides
consistency with what is already allowed
elsewhere in TSs. The isolation function of
the TIP [Traversing In-core Probe] valves is
mitigative, and does not create any increased
possibility of an accident. Also, the operation
of the manual shear valves is unaffected by
this activity. The ability to manually isolate
the TIP system by either the normal isolation
ball valves or the shear valves would be
unaffected by the inoperable
instrumentation. The Required Actions and
their associated Completion Times are not
initiating conditions for any accident
previously evaluated.
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.
No new accident scenarios, failure
mechanisms, or limiting single failures are
introduced as result of the proposed changes.
All systems, structures, and components
previously required for the mitigation of a
transient remain capable of fulfilling their
intended design functions. The proposed
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changes have no adverse effects on any
safety-related system or component and do
not challenge the performance or integrity of
any safety-related system. As a result no new
failure modes are being introduced.
Therefore, the proposed change does not
create the possibility of a new or different
kind of accident from any accident
previously evaluated.
3. Does the Proposed Change Involve a
Significant Reduction in a Margin of Safety?
Response: No.
The proposed change will not affect the
operation of plant equipment or the function
of any equipment assumed in the accident
analysis. The allowance to unisolate a
penetration flow path will not have a
significant effect on the margin of safety
because the penetration flow path can be
isolated manually, if needed. This change
provides consistency with what is already
allowed elsewhere in TSs. The option to
isolate a TIP penetration will ensure the
penetration will perform as designed in the
accident analysis. The ability to manually
isolate the TIP system is unaffected by the
inoperable instrumentation. The proposed
change does not impact any safety analysis
assumptions or results.
Therefore, the proposed change does not
result in a significant reduction in the margin
of safety.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 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: Bruce R.
Masters, DTE Energy, General Council—
Regulatory, 688 WCB, One Energy Plaza,
Detroit, MI 48226–1279.
NRC Acting Branch Chief: Shawn A.
Williams.
Entergy Nuclear Vermont Yankee (VY),
LLC and Entergy Nuclear Operations,
Inc., Docket No. 50–271, Vermont
Yankee Nuclear Power Station, Vernon,
Vermont
Date of amendment request:
December 22, 2011.
Description of amendment request:
The proposed amendment would revise
the Operating License (OL) Condition
3.S to allow Boiling Water Reactor
Vessels and Internal Project (BWRVIP)–
139–A ‘‘BWR Vessel and Internals
Project Steam Dryer Inspection and
Flaw Evaluation Guidelines’’ to be the
basis for future steam dryer monitoring
and inspections.
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
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consequences of an accident previously
evaluated?
Response: No.
The amendment does not significantly
increase the probability of an accident since
it does not involve a change to any plant
equipment that initiates a plant accident. The
change affects the standard by which future
steam dryer monitoring and structural
integrity inspections are performed. The
proposed standard has been approved for use
by the NRC. The steam dryer is not an
initiator or mitigator of any previously
evaluated accidents. Maintaining structural
integrity of the steam dryer ensures that
systems and components that are credited in
station safety analysis function as designed.
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 amendment does not involve
any physical alteration of plant equipment
and does not change the method by which
any safety-related system performs its
function. The change affects the standard by
which future steam dryer monitoring and
structural integrity inspections are
performed. The proposed standard has been
approved for use by the NRC. No new or
different types of equipment will be installed
and the basic operation of installed
equipment is unchanged. The methods
governing plant operation and testing remain
consistent with current safety analysis
assumptions.
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 amendment affects the
standard by which future steam dryer
monitoring and structural integrity
inspections are performed. The proposed
standard has been approved for use by the
NRC. The change does not affect design
codes or design margins. The change
provides for monitoring and inspection of the
steam dryer to ensure the dryer maintains its
integrity and does not affect safety related
equipment. This ensures analyzed safety
margins are maintained.
Therefore, operation of VY in accordance
with the proposed amendment will not
involve a significant reduction in the margin
to 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. William C.
Dennis, Assistant General Counsel,
Entergy Nuclear Operations, Inc., 400
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Hamilton Avenue, White Plains, NY
10601.
NRC Branch Chief: George Wilson.
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Entergy Nuclear Vermont Yankee (VY),
LLC and Entergy Nuclear Operations,
Inc., Docket No. 50–271, Vermont
Yankee Nuclear Power Station, Vernon,
Vermont
Date of amendment request: February
1, 2012.
Description of amendment request:
The proposed amendment would revise
Technical Specification (TS) 4.7.A.6.b to
allow the drywell to suppression
chamber leak rate test to be performed
once per operating cycle. No changes to
test acceptance criteria are proposed.
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 amendment does not
significantly increase the probability or
consequences of an accident since it does not
involve a modification to any plant
equipment or affect how plant systems or
components are operated. No design
functions or design parameters are affected
by the proposed amendment. The proposed
amendment involves the scheduling of a
surveillance requirement so that the affected
surveillance can be done anytime during the
operating cycle. The proposed amendment
does not impact the ability of the vacuum
breakers to function in the event of a LOCA
[loss-of-coolant accident] during the test.
Performance of the surveillance on line
versus during a refuel outage does not pose
a significant increase in risk. No changes to
the acceptance criteria for the surveillance
are proposed.
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 change involves the
schedule for performing a TS surveillance
requirement. The proposed change does not
change the method by which any safetyrelated system performs its function. No new
or different types of equipment will be
installed and the test will be performed
within the bounds of the TS requirements.
The methods governing plant operation and
testing remain consistent with current safety
analysis assumptions. The proposed
amendment involves the scheduling of a
surveillance requirement so that the affected
surveillance can be done anytime during the
operating cycle. No changes to acceptance
criteria for the surveillance are proposed.
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Therefore, the proposed change does not
create the possibility of a new or different
kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve
a significant reduction in a margin of safety?
Response: No.
The proposed amendment involves the
scheduling of a surveillance requirement so
that the affected surveillance can be done
anytime during the operating cycle. No
changes to the acceptance criteria for the
surveillance are proposed. The proposed
change ensures that the safety functions of
the pressure suppression chamber-drywell
vacuum breakers continue to be fulfilled by
performing the surveillance. The proposed
amendment does not involve a physical
modification of the plant and does not
change the design or function of any
component or system.
Therefore, the proposed amendment will
not involve a significant reduction in the
margin of safety.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 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. William C.
Dennis, Assistant General Counsel,
Entergy Nuclear Operations, Inc., 400
Hamilton Avenue, White Plains, NY
10601.
NRC Branch Chief: George Wilson.
Entergy Nuclear Vermont Yankee (VY),
LLC and Entergy Nuclear Operations,
Inc., Docket No. 50–271, Vermont
Yankee Nuclear Power Station, Vernon,
Vermont
Date of amendment request: March 5,
2012.
Description of amendment request:
The proposed amendment would revise
VY Renewed Facility Operating License
Condition (RFOLC) 3.P to clarify that
the programs and activities described in
the Updated Final Safety Analysis
Report (UFSAR) supplement submitted
pursuant to Title 10 of the Code of
Federal Regulations (10 CFR) 54.21(d),
as revised during the license renewal
application process, may be changed
without prior NRC approval provided
the requirements of 10 CFR 50.59 have
been previously satisfied. Additionally,
RFOLC 3.Q is revised to clarify that the
programs and activities, identified in
Appendix A of Supplement 2 to
NUREG–1907 and the UFSAR
supplement, to be completed before the
period of extended operation are
completed on schedule and the NRC is
to be notified upon completion of
implementation of these activities.
Basis for proposed no significant
hazards consideration determination:
PO 00000
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As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the
issue of no significant hazards
consideration which is presented below:
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The amendment does not significantly
increase the probability of an accident since
it does not involve a change to any plant
equipment that initiates a plant accident. The
change clarifies RFOLC 3.P and 3.Q. The
license conditions deal with administrative
controls over information contained in the
Updated Final Safety Analysis Report
(UFSAR) supplement. The proposed changes
are administrative and the license conditions
are not an initiator or mitigator of any
previously evaluated accidents.
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 amendment does not create
the possibility of a new or different kind of
accident from any accident previously
evaluated since it does not involve any
physical alteration of plant equipment and
does not change the method by which any
safety-related system performs its function.
The license conditions deal with
administrative controls over information
contained in the UFSAR supplement. No
new or different types of equipment will be
installed and the basic operation of installed
equipment is unchanged.
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 amendment does not affect
design codes or design margins. The change
clarifies RFOLC 3.P and 3.Q, is
administrative in nature and does not have
the ability to affect analyzed safety margins.
Therefore, operation of VY in accordance
with the proposed amendment will not
involve a significant reduction in the margin
to 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. William C.
Dennis, Assistant General Counsel,
Entergy Nuclear Operations, Inc., 400
Hamilton Avenue, White Plains, NY
10601.
NRC Branch Chief: George Wilson.
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PSEG Nuclear LLC, Docket No. 50–354,
Hope Creek Generating Station, Salem
County, New Jersey
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Date of amendment request: March 1,
2012.
Description of amendment request:
The proposed amendment would make
miscellaneous changes to the Technical
Specifications (TS) and Facility
Operating License (FOL) including: (1)
Correction of typographical errors; (2)
deletion of historical requirements that
have expired; (3) corrections of errors or
omissions from previous license
amendment requests; and (4) updating
of component lists to reflect current
plant design.
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
with Nuclear Regulatory Commission
(NRC) staff 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 changes to TS and the FOL
are administrative in nature that correct
typographical errors, or delete historical
requirements that have expired. These
changes do not affect the intent of any TS
requirements.
The proposed changes do not have any
impact on structures, systems and
components (SSCs) of the plant, and [have]
no effect on plant operations. The proposed
changes do not impact any accident initiators
or analyzed events or assumed mitigation of
accident or transient events. The proposed
changes to the technical specifications do not
result in the addition or removal of any
equipment but update component lists to
reflect equipment that was previously
removed or abandoned.
Therefore, these proposed changes do not
represent 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.
The proposed changes to TS and the FOL
are administrative in nature that correct
typographical errors, or delete historical
requirements that have expired. These
changes do not affect the intent of any TS
requirements.
The proposed changes do not involve a
modification to the physical configuration of
the plant (i.e., no new equipment will be
installed) or change in the methods
governing normal plant operation. The
proposed changes will not impose any new
or different requirements or introduce a new
accident initiator, accident precursor, or
malfunction mechanism.
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Additionally, there is no change in the
types or increases in the amounts of any
effluent that may be released off-site and
there is no increase in individual or
cumulative occupational exposure.
Therefore, the proposed changes do 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 proposed changes to TS and the FOL
are editorial in nature that correct
typographical errors, or delete historical
requirements that have expired. These
changes do not affect the intent of any TS
requirements.
The proposed changes incorporate
corrections to the TS and FOL and result in
improved accuracy of these licensing
documents. There is no change to any design
basis, licensing basis or safety limit, and no
change to any parameters; consequently no
safety margins are affected.
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, and with the changes noted
above in square brackets, 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: Jeffrie J. Keenan,
PSEG Nuclear LLC–N21, P.O. Box 236,
Hancocks Bridge, NJ 08038.
NRC Branch Chief: Meena K. Khanna.
Previously Published Notices of
Consideration of Issuance of
Amendments to Facility Operating
Licenses and Combined Licenses,
Proposed No Significant Hazards
Consideration Determination, and
Opportunity for a Hearing
The following notices were previously
published as separate individual
notices. The notice content was the
same as above. They were published as
individual notices either because time
did not allow the Commission to wait
for this biweekly notice or because the
action involved exigent circumstances.
They are repeated here because the
biweekly notice lists all amendments
issued or proposed to be issued
involving no significant hazards
consideration.
For details, see the individual notice
in the Federal Register on the day and
page cited. This notice does not extend
the notice period of the original notice.
PO 00000
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PPL Susquehanna, LLC, Docket No. 50–
388, Susquehanna Steam Electric
Station, Unit 2, Luzerne County,
Pennsylvania
Date of amendment request: March 8,
2012.
Description of amendment request:
The amendment allows a one-time
temporary extension of 24 hours to the
Completion Time for Condition C in the
Susquehanna Steam Electric Station
(SSES) Unit 2 Technical Specification
(TS) 3.8.7, ‘‘Distribution SystemsOperating,’’ to allow a Unit 1 4160 V
subsystem to be de-energized and
removed from service for 96 hours to
perform modifications on the bus. It also
allows a one-time temporary extension
of 24 hours to the Completion Time for
Condition A in SSES Unit 2 TS 3.7.1,
‘‘Plant Systems-RHRSW [residual heat
removal service water system] and UHS
[ultimate heat sink],’’ to allow the UHS
spray array and spray array bypass
valves associated with applicable
division RHRSW, and in Condition B,
the applicable division Unit 2 RHRSW
subsystem, to be inoperable for 96 hours
during the Unit 1 4160 V bus breaker
control logic modifications.
Date of publication of individual
notice in Federal Register: March 16,
2012 (77 FR 15814)
Expiration date of individual notice:
Comment period, April 16, 2012;
Hearing period, May 15, 2012.
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
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with 10 CFR 51.22. Therefore, pursuant
to 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared for these
amendments. If the Commission has
prepared an environmental assessment
under the special circumstances
provision in 10 CFR 51.22(b) and has
made a determination based on that
assessment, it is so indicated.
For further details with respect to the
action see (1) the applications for
amendment, (2) the amendment, and (3)
the Commission’s related letter, Safety
Evaluation and/or Environmental
Assessment as indicated. All of these
items are available for public inspection
at the NRC’s Public Document Room
(PDR), located at One White Flint North,
Room O1–F21, 11555 Rockville Pike
(first floor), Rockville, Maryland 20852.
Publicly available documents created or
received at the NRC are accessible
electronically through the Agencywide
Documents Access and Management
System (ADAMS) in the NRC Library at
https://www.nrc.gov/reading-rm/
adams.html. If you do not have access
to ADAMS or if there are problems in
accessing the documents located in
ADAMS, contact the PDR’s Reference
staff at 1–800–397–4209, 301–415–4737
or by email to pdr.resource@nrc.gov.
Duke Energy Carolinas, LLC, et al.,
Docket Nos. 50–413 and 50–414,
Catawba Nuclear Station, Units 1 and 2,
York County, South Carolina
Date of application for amendments:
June 30, 2011, as supplemented by
letters dated July 11, 2011, January 12,
2012, and February 1, 2012.
Brief description of amendments: The
amendments revised Technical
Specification (TS) 3.4.13, ‘‘RCS [Reactor
Coolant System] Operational
LEAKAGE,’’ TS 5.5.9, ‘‘Steam Generator
(SG) Program,’’ and TS 5.6.8, ‘‘Steam
Generator (SG) Tube Inspection Report.’’
Specifically, the amendments revised
the TSs to accomplish the following
objectives: permanently exclude
portions of a steam generator (SG) tube
below the top of the SG tubesheet from
periodic SG tube inspections and
plugging, permanently reduce the
primary-to-secondary leakage limit, and
permanently implement reporting
requirement changes that had been
previously established on a one-cycle
basis.
Date of issuance: March 12, 2012.
Effective date: As of the date of
issuance and shall be implemented
prior to entering the applicable Modes
of the affected TS at the completion of
the outage.
Amendment Nos.: Unit 1—267 and
Unit 2—263.
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Renewed Facility Operating License
Nos. NPF–35 and NPF–52: Amendments
revised the licenses and the technical
specifications.
Date of initial notice in Federal
Register: January 19, 2012 (77 FR
2766).
The supplemental letters dated July
11, 2011, January 12, 2012, and
February 1, 2012, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
consideration (NSHC) determination.
The Commission’s related evaluation
of the amendments and final NSHC
determination are contained in a Safety
Evaluation dated March 12, 2012.
No significant hazards consideration
comments received: No.
Exelon Generation Company, LLC,
Docket Nos. 50–352 and 50–353,
Limerick Generating Station, Units 1
and 2, Montgomery County,
Pennsylvania
Date of application for amendments:
June 2, 2011, as supplemented on
November 10, 2011.
Brief description of amendments: The
amendments revise the Technical
Specifications for each unit by changing
the method of calculating core reactivity
for the purpose of performing the
reactivity anomaly surveillance at
Limerick Generating Station, Units 1
and 2. The change allows performance
of the surveillance based on a
comparison of predicted to actual
(monitored) core reactivity. The
reactivity anomaly verification was
previously determined by a comparison
of predicted versus actual control rod
density.
Date of issuance: March 14, 2012.
Effective date: As of the date of
issuance, and shall be implemented
within 60 days.
Amendment Nos.: 207 and 168.
Facility Operating License Nos. NPF–
39 and NPF–85. These amendments
revised the license and the technical
specifications.
Date of initial notice in Federal
Register: August 9, 2011 (76 FR 48911).
The supplement dated November 10,
2011, clarified the application, did not
expand the scope of the application as
originally noticed, and did not change
the initial proposed no significant
hazards consideration determination.
The Commission’s related evaluation
of the amendment is contained in Safety
Evaluation dated March 14, 2012.
No significant hazards consideration
comments received: No.
Attorney for licensee: J. Bradley
Fewell, Esquire, Associate General
PO 00000
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Counsel, Exelon Generation Company,
LLC, 4300 Winfield Road, Warrenville,
IL 60555.
NRC Branch Chief: Meena Khanna.
Exelon Generation Company, LLC,
Docket No. 50–254, Quad Cities Nuclear
Power Station, Unit 1, Rock Island
County, Illinois
Date of application for amendment:
June 7, 2011, as supplemented by letters
dated. September 21, 2011, November 2,
2011, and January 9, 2012.
Brief description of amendment: The
amendment revises the value of the
single recirculation loop operation
(SLO) safety limit minimum critical
power ratio (SLMCPR) in Technical
Specifications Section 2.1.1, ‘‘Reactor
Core SLs [Safety Limits].’’ Specifically,
the revision replaces the current SLO
SLMCPR requirement for QCNPS Unit 1
with a new SLMCPR requirement. The
revision is necessary because of errors
that were discovered in the
Westinghouse McSLAP computer code
that resulted in a non-conservative SLO
SLMCPR.
Date of issuance: March 8, 2012.
Effective date: As of the date of
issuance and shall be implemented
within 30 days.
Amendment No.: 250.
Renewed Facility Operating License
Nos. DPR–29: The amendments revised
the Technical Specifications and
License.
Date of initial notice in Federal
Register: August 16, 2011 (72 FR
50762).
The September 21, 2011, November 2,
2011, and January 9, 2012, supplements
contained clarifying information and
did not change the NRC staff’s initial
proposed finding of no significant
hazards consideration.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated March 12, 2012.
No significant hazards consideration
comments received: No.
Exelon Generation Company, LLC,
Docket No. 50–265, Quad Cities Nuclear
Power Station, Unit 2, Rock Island
County, Illinois
Date of application for amendment:
November 22, 2011, as supplemented by
letter dated January 9, 2012.
Brief description of amendment: The
amendment revises the value of the
single recirculation loop operation
(SLO) and dual recirculation loop
operation (DLO) safety limit minimum
critical power ratio (SLMCPR) in
Technical Specifications Section 2.1.1,
‘‘Reactor Core SLs [Safety Limits].’’
Specifically, the revision replaces the
current SLO and DLO SLMCPR
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requirement for QCNPS Unit 2 with a
new SLMCPR requirement. The revision
is necessary because of errors that were
discovered in the Westinghouse
McSLAP computer code that resulted in
non-conservative SLMCPR.values.
Date of issuance: March 8, 2012.
Effective date: As of the date of
issuance and shall be implemented
within 30 days.
Amendment No.: 245.
Renewed Facility Operating License
Nos. DPR–30: The amendments revised
the Technical Specifications and
License.
Date of initial notice in Federal
Register: January 3, 2012 (77 FR 140).
The January 9, 2012, supplement,
contained clarifying information and
did not change the NRC staff’s initial
proposed finding of no significant
hazards consideration.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated March 8, 2012.
No significant hazards consideration
comments received: No.
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FirstEnergy Nuclear Operating
Company, et al., Docket Nos. 50–334
and 50–412, Beaver Valley Power
Station, Unit Nos. 1 and 2 (BVPS–1 and
2), Beaver County, Pennsylvania
Date of application for amendment:
May 27, 2011.
Brief description of amendment: The
amendments revise Technical
Specifications (TSs) associated with
replacing sodium hydroxide with
sodium tetraborate as a chemical
additive for containment sump pH
control following a loss-of-coolant
accident at BVPS–1. Due to common
TSs for BVPS–1 and 2, administrative
changes were made to BVPS–2 license
to reflect the BVPS–1 changes.
Date of issuance: March 14, 2012.
Effective date: As of the date of
issuance and shall be implemented
prior to achieving Mode 4 during
startup from the BVPS–1 refueling
outage in the spring of 2012.
Amendment Nos.: 289 and 176.
Facility Operating License Nos. DPR–
66 and NPF–73: Amendments revise the
Licenses and TSs.
Date of initial notice in Federal
Register: January 10, 2012 (77 FR
1518).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated March 14, 2012.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 23rd day
of March 2012.
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For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2012–7676 Filed 4–2–12; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0002]
Sunshine Federal Register Notice
AGENCY HOLDING THE MEETINGS: Nuclear
Regulatory Commission.
DATE: Weeks of April 2, 9, 16, 23, 30,
May 7, 2012.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
Week of April 2, 2012
Tuesday April 3, 2012
9:30 a.m. Meeting with Organization of
Agreement States (OAS) and
Conference of Radiation Control
Program Directors (CRCPD) (Public
Meeting) (Contact: Cindy Flannery,
301–415–0223).
This meeting will be webcast live at
the Web address—www.nrc.gov.
Week of April 9, 2012—Tentative
Tuesday, April 10, 2012
9 a.m. Briefing on the Final Report of
the Blue Ribbon Commission on
America’s Nuclear Future (Public
Meeting) (Contact: Alicia Mullins,
301–492–3351).
This meeting will be webcast live at
the Web address—www.nrc.gov.
Week of April 16, 2012—Tentative
There are no meetings scheduled for
the week of April 16, 2012.
Week of April 23, 2012—Tentative
Tuesday, April 24, 2012
9 a.m. Briefing on Part 35 Medical
Events Definitions—Permanent
Implant Brachytherapy (Contact:
Michael Fuller, 301–415–0520).
This meeting will be webcast live at
the Web address—www.nrc.gov.
Week of April 30, 2012—Tentative
Monday, April 30, 2012
9:30 a.m. Briefing on Human Capital
and Equal Employment
Opportunity (EEO) (Public Meeting)
(Contact: Kristin Davis, 301–492–
2208).
This meeting will be webcast live at
the Web address—www.nrc.gov.
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20077
Week of May 7, 2012—Tentative
Friday, May 11, 2012
9 a.m. Briefing on Potential Medical
Isotope Production Licensing
Actions (Public Meeting) (Contact:
Jessie Quichocho, 301–415–0209).
This meeting will be webcast live at
the Web address—www.nrc.gov.
*The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—301–415–1292.
Contact person for more information:
Rochelle Bavol, 301–415–1651.
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify Bill
Dosch, Chief, Work Life and Benefits
Branch, at 301–415–6200, TDD: 301–
415–2100, or by email at
william.dosch@nrc.gov. Determinations
on requests for reasonable
accommodation will be made on a caseby-case basis.
This notice is distributed
electronically to subscribers. If you no
longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301–415–1969),
or send an email to
darlene.wright@nrc.gov.
Dated: March 29, 2012.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2012–8077 Filed 3–30–12; 4:15 pm]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Request for a License To Export
Radioactive Waste
Pursuant to 10 CFR 110.70 (b) ‘‘Public
Notice of Receipt of an Application,’’
please take notice that the Nuclear
Regulatory Commission (NRC) has
received the following request for an
export license. Copies of the request are
available electronically through ADAMS
and can be accessed through the Public
Electronic Reading Room (PERR) link
https://www.nrc.gov/reading-rm.html at
the NRC Homepage.
A request for a hearing or petition for
leave to intervene may be filed within
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Agencies
[Federal Register Volume 77, Number 64 (Tuesday, April 3, 2012)]
[Notices]
[Pages 20070-20077]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-7676]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0078]
Biweekly Notice of 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 (the
Commission or NRC) is publishing this regular biweekly notice. The Act
requires the Commission publish notice of any amendments issued, or
proposed to be issued and grants the Commission the authority to issue
and make immediately effective any amendment to an operating license 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 March 8, 2012, to March 21, 2012. The last
biweekly notice was published on March 20, 2012 (77 FR 16271).
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and is publicly available, by
searching on https://www.regulations.gov under Docket ID 2012-0078.
You may submit comments by the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID 2012-0078. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
Fax comments to: RADB at 301-492-3446.
For additional direction on accessing information and submitting
comments, see ``Accessing Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID 2012-0078 when contacting the NRC about
the availability of information regarding this document. You may access
information related to this document, which the NRC possesses and is
publicly available, by the following methods:
Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for Docket ID 2012-0078.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. Documents may be viewed in
ADAMS by performing a search on the document date and docket number.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One
[[Page 20071]]
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID 2012-0078 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information in comment submissions that you do not want to be publicly
disclosed. The NRC posts all comment submissions at https://www.regulations.gov as well as entering the comment submissions into
ADAMS, and the NRC does not edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information in their comment submissions
that they do not want to be publicly disclosed. Your request should
state that the NRC will not edit comment submissions to remove such
information before making the comment submissions available to the
public or entering the comment submissions into ADAMS.
Notice of Consideration of Issuance of Amendments to Facility Operating
Licenses 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 Title 10 of the Code of Federal
Regulations (10 CFR) 50.92, this means that operation of the facility
in accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; 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 ``Rules of
Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2.
Interested person(s) should consult a current copy of 10 CFR 2.309,
which is available at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. The NRC regulations are accessible electronically from the NRC
Library on the NRC's Web site at https://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to
intervene is filed by the above date, the Commission or a presiding
officer designated by the Commission or by the Chief Administrative
Judge of the Atomic Safety and Licensing Board Panel, will rule on the
request and/or petition; and the Secretary or the Chief Administrative
Judge of the Atomic Safety and Licensing Board will issue a notice of a
hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the applicant on a material issue of law
or fact. Contentions shall be limited to matters within the scope of
the amendment under consideration. The contention must be one which, if
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held
[[Page 20072]]
would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the Internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at hearing.docket@nrc.gov, or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at https://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with the NRC guidance
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC Web site
at https://www.nrc.gov/site-help/e-submittals.html, by email at
MSHD.Resource@nrc.gov, or by a toll-free call at 1-866 672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852, Attention: Rulemaking and Adjudications Staff. Participants
filing a document in this manner are responsible for serving the
document on all other participants. Filing is considered complete by
first-class mail as of the time of deposit in the mail, or by courier,
express mail, or expedited delivery service upon depositing the
document with the provider of the service. A presiding officer, having
granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information. With
respect to copyrighted works, except for limited excerpts that serve
the purpose of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Non-timely filings
will not be entertained absent a determination by the presiding officer
that the petition or request should be granted or the contentions
should be admitted, based on a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents
[[Page 20073]]
created or received at the NRC are accessible electronically through
ADAMS in the NRC Library at https://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who encounter problems in
accessing the documents located in ADAMS, should contact the NRC's PDR
Reference staff at 1-800-397-4209, 301-415-4737, or by email to
pdr.resource@nrc.gov.
Detroit Edison, Docket No. 50-341, Fermi 2, Monroe County, Michigan
Date of amendment request: December 20, 2011.
Description of amendment request: The proposed amendment would
modify Technical Specifications requirements related to primary
containment isolation instrumentation. The changes are in accordance
with Nuclear Regulatory Commission approved Technical Specification
Task Force (TSTF), Improved Standard Technical Specifications change
TSTF-306, Revision 2.
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 addition of the note that the penetration flow path may be
unisolated under administrative control provides consistency with
what is already allowed elsewhere in TSs. The isolation function of
the TIP [Traversing In-core Probe] valves is mitigative, and does
not create any increased possibility of an accident. Also, the
operation of the manual shear valves is unaffected by this activity.
The ability to manually isolate the TIP system by either the normal
isolation ball valves or the shear valves would be unaffected by the
inoperable instrumentation. The Required Actions and their
associated Completion Times are not initiating conditions for any
accident previously evaluated.
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.
No new accident scenarios, failure mechanisms, or limiting
single failures are introduced as result of the proposed changes.
All systems, structures, and components previously required for the
mitigation of a transient remain capable of fulfilling their
intended design functions. The proposed changes have no adverse
effects on any safety-related system or component and do not
challenge the performance or integrity of any safety-related system.
As a result no new failure modes are being introduced.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the Proposed Change Involve a Significant Reduction in a
Margin of Safety?
Response: No.
The proposed change will not affect the operation of plant
equipment or the function of any equipment assumed in the accident
analysis. The allowance to unisolate a penetration flow path will
not have a significant effect on the margin of safety because the
penetration flow path can be isolated manually, if needed. This
change provides consistency with what is already allowed elsewhere
in TSs. The option to isolate a TIP penetration will ensure the
penetration will perform as designed in the accident analysis. The
ability to manually isolate the TIP system is unaffected by the
inoperable instrumentation. The proposed change does not impact any
safety analysis assumptions or results.
Therefore, the proposed change does not result in a significant
reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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: Bruce R. Masters, DTE Energy, General
Council--Regulatory, 688 WCB, One Energy Plaza, Detroit, MI 48226-1279.
NRC Acting Branch Chief: Shawn A. Williams.
Entergy Nuclear Vermont Yankee (VY), LLC and Entergy Nuclear
Operations, Inc., Docket No. 50-271, Vermont Yankee Nuclear Power
Station, Vernon, Vermont
Date of amendment request: December 22, 2011.
Description of amendment request: The proposed amendment would
revise the Operating License (OL) Condition 3.S to allow Boiling Water
Reactor Vessels and Internal Project (BWRVIP)-139-A ``BWR Vessel and
Internals Project Steam Dryer Inspection and Flaw Evaluation
Guidelines'' to be the basis for future steam dryer monitoring and
inspections.
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 amendment does not significantly increase the probability of
an accident since it does not involve a change to any plant
equipment that initiates a plant accident. The change affects the
standard by which future steam dryer monitoring and structural
integrity inspections are performed. The proposed standard has been
approved for use by the NRC. The steam dryer is not an initiator or
mitigator of any previously evaluated accidents. Maintaining
structural integrity of the steam dryer ensures that systems and
components that are credited in station safety analysis function as
designed.
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 amendment does not involve any physical alteration
of plant equipment and does not change the method by which any
safety-related system performs its function. The change affects the
standard by which future steam dryer monitoring and structural
integrity inspections are performed. The proposed standard has been
approved for use by the NRC. No new or different types of equipment
will be installed and the basic operation of installed equipment is
unchanged. The methods governing plant operation and testing remain
consistent with current safety analysis assumptions.
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 amendment affects the standard by which future
steam dryer monitoring and structural integrity inspections are
performed. The proposed standard has been approved for use by the
NRC. The change does not affect design codes or design margins. The
change provides for monitoring and inspection of the steam dryer to
ensure the dryer maintains its integrity and does not affect safety
related equipment. This ensures analyzed safety margins are
maintained.
Therefore, operation of VY in accordance with the proposed
amendment will not involve a significant reduction in the margin to
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. William C. Dennis, Assistant General
Counsel, Entergy Nuclear Operations, Inc., 400
[[Page 20074]]
Hamilton Avenue, White Plains, NY 10601.
NRC Branch Chief: George Wilson.
Entergy Nuclear Vermont Yankee (VY), LLC and Entergy Nuclear
Operations, Inc., Docket No. 50-271, Vermont Yankee Nuclear Power
Station, Vernon, Vermont
Date of amendment request: February 1, 2012.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) 4.7.A.6.b to allow the drywell to
suppression chamber leak rate test to be performed once per operating
cycle. No changes to test acceptance criteria are proposed.
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 amendment does not significantly increase the
probability or consequences of an accident since it does not involve
a modification to any plant equipment or affect how plant systems or
components are operated. No design functions or design parameters
are affected by the proposed amendment. The proposed amendment
involves the scheduling of a surveillance requirement so that the
affected surveillance can be done anytime during the operating
cycle. The proposed amendment does not impact the ability of the
vacuum breakers to function in the event of a LOCA [loss-of-coolant
accident] during the test. Performance of the surveillance on line
versus during a refuel outage does not pose a significant increase
in risk. No changes to the acceptance criteria for the surveillance
are proposed.
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 change involves the schedule for performing a TS
surveillance requirement. The proposed change does not change the
method by which any safety-related system performs its function. No
new or different types of equipment will be installed and the test
will be performed within the bounds of the TS requirements. The
methods governing plant operation and testing remain consistent with
current safety analysis assumptions. The proposed amendment involves
the scheduling of a surveillance requirement so that the affected
surveillance can be done anytime during the operating cycle. No
changes to acceptance criteria for the surveillance are proposed.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed amendment involves the scheduling of a surveillance
requirement so that the affected surveillance can be done anytime
during the operating cycle. No changes to the acceptance criteria
for the surveillance are proposed. The proposed change ensures that
the safety functions of the pressure suppression chamber-drywell
vacuum breakers continue to be fulfilled by performing the
surveillance. The proposed amendment does not involve a physical
modification of the plant and does not change the design or function
of any component or system.
Therefore, the proposed amendment will not involve a significant
reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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. William C. Dennis, Assistant General
Counsel, Entergy Nuclear Operations, Inc., 400 Hamilton Avenue, White
Plains, NY 10601.
NRC Branch Chief: George Wilson.
Entergy Nuclear Vermont Yankee (VY), LLC and Entergy Nuclear
Operations, Inc., Docket No. 50-271, Vermont Yankee Nuclear Power
Station, Vernon, Vermont
Date of amendment request: March 5, 2012.
Description of amendment request: The proposed amendment would
revise VY Renewed Facility Operating License Condition (RFOLC) 3.P to
clarify that the programs and activities described in the Updated Final
Safety Analysis Report (UFSAR) supplement submitted pursuant to Title
10 of the Code of Federal Regulations (10 CFR) 54.21(d), as revised
during the license renewal application process, may be changed without
prior NRC approval provided the requirements of 10 CFR 50.59 have been
previously satisfied. Additionally, RFOLC 3.Q is revised to clarify
that the programs and activities, identified in Appendix A of
Supplement 2 to NUREG-1907 and the UFSAR supplement, to be completed
before the period of extended operation are completed on schedule and
the NRC is to be notified upon completion of implementation of these
activities.
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 amendment does not significantly increase the probability of
an accident since it does not involve a change to any plant
equipment that initiates a plant accident. The change clarifies
RFOLC 3.P and 3.Q. The license conditions deal with administrative
controls over information contained in the Updated Final Safety
Analysis Report (UFSAR) supplement. The proposed changes are
administrative and the license conditions are not an initiator or
mitigator of any previously evaluated accidents.
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 amendment does not create the possibility of a new
or different kind of accident from any accident previously evaluated
since it does not involve any physical alteration of plant equipment
and does not change the method by which any safety-related system
performs its function. The license conditions deal with
administrative controls over information contained in the UFSAR
supplement. No new or different types of equipment will be installed
and the basic operation of installed equipment is unchanged.
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 amendment does not affect design codes or design
margins. The change clarifies RFOLC 3.P and 3.Q, is administrative
in nature and does not have the ability to affect analyzed safety
margins.
Therefore, operation of VY in accordance with the proposed
amendment will not involve a significant reduction in the margin to
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. William C. Dennis, Assistant General
Counsel, Entergy Nuclear Operations, Inc., 400 Hamilton Avenue, White
Plains, NY 10601.
NRC Branch Chief: George Wilson.
[[Page 20075]]
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station,
Salem County, New Jersey
Date of amendment request: March 1, 2012.
Description of amendment request: The proposed amendment would make
miscellaneous changes to the Technical Specifications (TS) and Facility
Operating License (FOL) including: (1) Correction of typographical
errors; (2) deletion of historical requirements that have expired; (3)
corrections of errors or omissions from previous license amendment
requests; and (4) updating of component lists to reflect current plant
design.
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 with Nuclear Regulatory
Commission (NRC) staff 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 changes to TS and the FOL are administrative in
nature that correct typographical errors, or delete historical
requirements that have expired. These changes do not affect the
intent of any TS requirements.
The proposed changes do not have any impact on structures,
systems and components (SSCs) of the plant, and [have] no effect on
plant operations. The proposed changes do not impact any accident
initiators or analyzed events or assumed mitigation of accident or
transient events. The proposed changes to the technical
specifications do not result in the addition or removal of any
equipment but update component lists to reflect equipment that was
previously removed or abandoned.
Therefore, these proposed changes do not represent 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.
The proposed changes to TS and the FOL are administrative in
nature that correct typographical errors, or delete historical
requirements that have expired. These changes do not affect the
intent of any TS requirements.
The proposed changes do not involve a modification to the
physical configuration of the plant (i.e., no new equipment will be
installed) or change in the methods governing normal plant
operation. The proposed changes will not impose any new or different
requirements or introduce a new accident initiator, accident
precursor, or malfunction mechanism.
Additionally, there is no change in the types or increases in
the amounts of any effluent that may be released off-site and there
is no increase in individual or cumulative occupational exposure.
Therefore, the proposed changes do 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 proposed changes to TS and the FOL are editorial in nature
that correct typographical errors, or delete historical requirements
that have expired. These changes do not affect the intent of any TS
requirements.
The proposed changes incorporate corrections to the TS and FOL
and result in improved accuracy of these licensing documents. There
is no change to any design basis, licensing basis or safety limit,
and no change to any parameters; consequently no safety margins are
affected.
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, and with the changes noted above in square brackets, 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: Jeffrie J. Keenan, PSEG Nuclear LLC-N21,
P.O. Box 236, Hancocks Bridge, NJ 08038.
NRC Branch Chief: Meena K. Khanna.
Previously Published Notices of Consideration of Issuance of Amendments
to Facility Operating Licenses and Combined Licenses, Proposed No
Significant Hazards Consideration Determination, and Opportunity for a
Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
PPL Susquehanna, LLC, Docket No. 50-388, Susquehanna Steam Electric
Station, Unit 2, Luzerne County, Pennsylvania
Date of amendment request: March 8, 2012.
Description of amendment request: The amendment allows a one-time
temporary extension of 24 hours to the Completion Time for Condition C
in the Susquehanna Steam Electric Station (SSES) Unit 2 Technical
Specification (TS) 3.8.7, ``Distribution Systems-Operating,'' to allow
a Unit 1 4160 V subsystem to be de-energized and removed from service
for 96 hours to perform modifications on the bus. It also allows a one-
time temporary extension of 24 hours to the Completion Time for
Condition A in SSES Unit 2 TS 3.7.1, ``Plant Systems-RHRSW [residual
heat removal service water system] and UHS [ultimate heat sink],'' to
allow the UHS spray array and spray array bypass valves associated with
applicable division RHRSW, and in Condition B, the applicable division
Unit 2 RHRSW subsystem, to be inoperable for 96 hours during the Unit 1
4160 V bus breaker control logic modifications.
Date of publication of individual notice in Federal Register: March
16, 2012 (77 FR 15814)
Expiration date of individual notice: Comment period, April 16,
2012; Hearing period, May 15, 2012.
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
[[Page 20076]]
with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no
environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection at
the NRC's Public Document Room (PDR), located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by email to
pdr.resource@nrc.gov.
Duke Energy Carolinas, LLC, et al., Docket Nos. 50-413 and 50-414,
Catawba Nuclear Station, Units 1 and 2, York County, South Carolina
Date of application for amendments: June 30, 2011, as supplemented
by letters dated July 11, 2011, January 12, 2012, and February 1, 2012.
Brief description of amendments: The amendments revised Technical
Specification (TS) 3.4.13, ``RCS [Reactor Coolant System] Operational
LEAKAGE,'' TS 5.5.9, ``Steam Generator (SG) Program,'' and TS 5.6.8,
``Steam Generator (SG) Tube Inspection Report.'' Specifically, the
amendments revised the TSs to accomplish the following objectives:
permanently exclude portions of a steam generator (SG) tube below the
top of the SG tubesheet from periodic SG tube inspections and plugging,
permanently reduce the primary-to-secondary leakage limit, and
permanently implement reporting requirement changes that had been
previously established on a one-cycle basis.
Date of issuance: March 12, 2012.
Effective date: As of the date of issuance and shall be implemented
prior to entering the applicable Modes of the affected TS at the
completion of the outage.
Amendment Nos.: Unit 1--267 and Unit 2--263.
Renewed Facility Operating License Nos. NPF-35 and NPF-52:
Amendments revised the licenses and the technical specifications.
Date of initial notice in Federal Register: January 19, 2012 (77 FR
2766).
The supplemental letters dated July 11, 2011, January 12, 2012, and
February 1, 2012, provided additional information that clarified the
application, did not expand the scope of the application as originally
noticed, and did not change the staff's original proposed no
significant hazards consideration (NSHC) determination.
The Commission's related evaluation of the amendments and final
NSHC determination are contained in a Safety Evaluation dated March 12,
2012.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
Date of application for amendments: June 2, 2011, as supplemented
on November 10, 2011.
Brief description of amendments: The amendments revise the
Technical Specifications for each unit by changing the method of
calculating core reactivity for the purpose of performing the
reactivity anomaly surveillance at Limerick Generating Station, Units 1
and 2. The change allows performance of the surveillance based on a
comparison of predicted to actual (monitored) core reactivity. The
reactivity anomaly verification was previously determined by a
comparison of predicted versus actual control rod density.
Date of issuance: March 14, 2012.
Effective date: As of the date of issuance, and shall be
implemented within 60 days.
Amendment Nos.: 207 and 168.
Facility Operating License Nos. NPF-39 and NPF-85. These amendments
revised the license and the technical specifications.
Date of initial notice in Federal Register: August 9, 2011 (76 FR
48911).
The supplement dated November 10, 2011, clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the initial proposed no significant hazards
consideration determination.
The Commission's related evaluation of the amendment is contained
in Safety Evaluation dated March 14, 2012.
No significant hazards consideration comments received: No.
Attorney for licensee: J. Bradley Fewell, Esquire, Associate
General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road,
Warrenville, IL 60555.
NRC Branch Chief: Meena Khanna.
Exelon Generation Company, LLC, Docket No. 50-254, Quad Cities Nuclear
Power Station, Unit 1, Rock Island County, Illinois
Date of application for amendment: June 7, 2011, as supplemented by
letters dated. September 21, 2011, November 2, 2011, and January 9,
2012.
Brief description of amendment: The amendment revises the value of
the single recirculation loop operation (SLO) safety limit minimum
critical power ratio (SLMCPR) in Technical Specifications Section
2.1.1, ``Reactor Core SLs [Safety Limits].'' Specifically, the revision
replaces the current SLO SLMCPR requirement for QCNPS Unit 1 with a new
SLMCPR requirement. The revision is necessary because of errors that
were discovered in the Westinghouse McSLAP computer code that resulted
in a non-conservative SLO SLMCPR.
Date of issuance: March 8, 2012.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment No.: 250.
Renewed Facility Operating License Nos. DPR-29: The amendments
revised the Technical Specifications and License.
Date of initial notice in Federal Register: August 16, 2011 (72 FR
50762).
The September 21, 2011, November 2, 2011, and January 9, 2012,
supplements contained clarifying information and did not change the NRC
staff's initial proposed finding of no significant hazards
consideration.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 12, 2012.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-265, Quad Cities Nuclear
Power Station, Unit 2, Rock Island County, Illinois
Date of application for amendment: November 22, 2011, as
supplemented by letter dated January 9, 2012.
Brief description of amendment: The amendment revises the value of
the single recirculation loop operation (SLO) and dual recirculation
loop operation (DLO) safety limit minimum critical power ratio (SLMCPR)
in Technical Specifications Section 2.1.1, ``Reactor Core SLs [Safety
Limits].'' Specifically, the revision replaces the current SLO and DLO
SLMCPR
[[Page 20077]]
requirement for QCNPS Unit 2 with a new SLMCPR requirement. The
revision is necessary because of errors that were discovered in the
Westinghouse McSLAP computer code that resulted in non-conservative
SLMCPR.values.
Date of issuance: March 8, 2012.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment No.: 245.
Renewed Facility Operating License Nos. DPR-30: The amendments
revised the Technical Specifications and License.
Date of initial notice in Federal Register: January 3, 2012 (77 FR
140).
The January 9, 2012, supplement, contained clarifying information
and did not change the NRC staff's initial proposed finding of no
significant hazards consideration.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated March 8, 2012.
No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and
50-412, Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2),
Beaver County, Pennsylvania
Date of application for amendment: May 27, 2011.
Brief description of amendment: The amendments revise Technical
Specifications (TSs) associated with replacing sodium hydroxide with
sodium tetraborate as a chemical additive for containment sump pH
control following a loss-of-coolant accident at BVPS-1. Due to common
TSs for BVPS-1 and 2, administrative changes were made to BVPS-2
license to reflect the BVPS-1 changes.
Date of issuance: March 14, 2012.
Effective date: As of the date of issuance and shall be implemented
prior to achieving Mode 4 during startup from the BVPS-1 refueling
outage in the spring of 2012.
Amendment Nos.: 289 and 176.
Facility Operating License Nos. DPR-66 and NPF-73: Amendments
revise the Licenses and TSs.
Date of initial notice in Federal Register: January 10, 2012 (77 FR
1518).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated March 14, 2012.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 23rd day of March 2012.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2012-7676 Filed 4-2-12; 8:45 am]
BILLING CODE 7590-01-P