[Federal Register Volume 76, Number 143 (Tuesday, July 26, 2011)]
[Notices]
[Pages 44614-44619]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-18525]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2011-0167]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses Involving No Significant Hazards Considerations
Background
Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (the
Commission or NRC) is publishing this regular biweekly notice. The Act
requires the Commission publish notice of any amendments issued, or
proposed to be issued and grants the Commission the authority to issue
and make immediately effective any amendment to an operating license
upon a determination by the Commission that such amendment involves no
significant hazards consideration, notwithstanding the pendency before
the Commission of a request for a hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued from June 30, 2011 to July 13, 2011. The last
biweekly notice was published on July 12, 2011 (76 FR 40937).
ADDRESSES: Please include Docket ID NRC-2011-0167 in the subject line
of your comments. Comments submitted in writing or in electronic form
will be posted on the NRC Web site and on the Federal rulemaking Web
site http://www.regulations.gov. Because your comments will not be
edited to remove any identifying or contact information, the NRC
cautions you against including any information in your submission that
you do not want to be publicly disclosed.
The NRC requests that any party soliciting or aggregating comments
received from other persons for submission to the NRC inform those
persons that the NRC will not edit their comments to remove any
identifying or contact information, and therefore, they should not
include any information in their comments that they do not want
publicly disclosed.
You may submit comments by any one of the following methods.
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC-
NRC-2011-0167. Address questions about NRC dockets to Carol Gallagher
301-492-3668; e-mail [email protected].
Mail comments to: 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.
You can access publicly available documents related to this notice
using the following methods:
NRC's Public Document Room (PDR): The public may examine
and have copied, for a fee, publicly available documents at the NRC's
PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland 20852.
NRC's Agencywide Documents Access and Management System
(ADAMS): Publicly available documents created or received at the NRC
are accessible electronically through ADAMS in the NRC Library at
http://www.nrc.gov/reading-rm/adams.html. From this page, the public
can gain entry into ADAMS, which provides text and image files of the
NRC's public documents. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
NRC's PDR reference staff at 1-800-397-4209, 301-415-4737, or by e-mail
to [email protected].
Federal Rulemaking Web site: Public comments and
supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC-2011-0167.
Notice of Consideration of Issuance of Amendments to Facility Operating
Licenses, Proposed No Significant Hazards Consideration Determination,
and Opportunity for a Hearing
The Commission has made a proposed determination that the following
amendment requests involve no significant hazards consideration. Under
the Commission's regulations in Title 10 of the Code of Federal
Regulations (10 CFR), 50.92, this means that operation of the facility
in accordance with the proposed amendment would not (1) Involve a
significant increase in the probability or
[[Page 44615]]
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.
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. NRC
regulations are accessible electronically from the NRC Library on the
NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If
a request for a hearing or petition for leave to intervene is filed by
the above date, the Commission or a presiding officer designated by the
Commission or by the Chief Administrative Judge of the Atomic Safety
and Licensing Board Panel, will rule on the request and/or petition;
and the Secretary or the Chief Administrative Judge of the Atomic
Safety and Licensing Board will issue a notice of a hearing or an
appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the applicant on a material issue of law
or fact. Contentions shall be limited to matters within the scope of
the amendment under consideration. The contention must be one which, if
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC 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 e-mail at [email protected], or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System
[[Page 44616]]
requirements for accessing the E-Submittal server are detailed in NRC's
``Guidance for Electronic Submission,'' which is available on the
agency's public Web site at http://www.nrc.gov/site-help/e-submittals.html. Participants may attempt to use other software not
listed on the Web site, but should note that the NRC's E-Filing system
does not support unlisted software, and the NRC Meta System Help Desk
will not be able to offer assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with NRC guidance
available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an e-mail notice confirming receipt of the document. The
E-Filing system also distributes an e-mail notice that provides access
to the document to the NRC 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 http://www.nrc.gov/site-help/e-submittals.html, by e-mail at
[email protected], or by a toll-free call at 1-866-672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) first class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852, Attention: Rulemaking and Adjudications Staff. Participants
filing a document in this manner are responsible for serving the
document on all other participants. Filing is considered complete by
first-class mail as of the time of deposit in the mail, or by courier,
express mail, or expedited delivery service upon depositing the
document with the provider of the service. A presiding officer, having
granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd1.nrc.gov/EHD/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information. With
respect to copyrighted works, except for limited excerpts that serve
the purpose of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Non-timely filings
will not be entertained absent a determination by the presiding officer
that the petition or request should be granted or the contentions
should be admitted, based on a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC PDR Reference staff at 1-800-397-4209,
301-415-4737, or by e-mail to [email protected].
Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc.,
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish,
Louisiana
Date of amendment request: June 10, 2011.
Description of amendment request: The proposed amendment would
revise the Technical Specifications (TSs) to add a new limiting
condition for operation (LCO) Applicability requirement, LCO 3.0.9, and
its associated Bases, relating to the modification of requirements
regarding the impact of unavailable barriers, not explicitly addressed
in TSs, but required for operability of supported systems in TSs. This
change is consistent with NRC-approved Technical Specification Task
Force (TSTF) Improved Standard Technical Specification Change Traveler,
TSTF-427, Revision 2, ``Allowance for Non Technical Specification
Barrier Degradation on Supported System OPERABILITY.''
The NRC staff issued a Notice of Opportunity to Comment in the
Federal Register on June 2, 2006 (71 FR 32145), on possible amendments
to revise the plant-specific TSs, including a model safety evaluation
and model no significant hazards consideration determination using the
consolidated line item improvement process. The NRC staff subsequently
issued a Notice of Availability of this TS improvement in the Federal
Register on October 3, 2006 (71 FR 58444). The licensee affirmed the
applicability of the model no significant hazards consideration
[[Page 44617]]
determination in its application dated June 10, 2011.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of no significant hazards consideration is presented below:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change allows a delay time for entering a supported
system technical specification (TS) when the inoperability is due
solely to an unavailable barrier if risk is assessed and managed. The
postulated initiating events which may require a functional barrier are
limited to those with low frequencies of occurrence, and the overall TS
system safety function would still be available for the majority of
anticipated challenges. Therefore, the probability of an accident
previously evaluated is not significantly increased, if at all. The
consequences of an accident while relying on the allowance provided by
proposed LCO 3.0.9 are no different than the consequences of an
accident while relying on the TS required actions in effect without the
allowance provided by proposed LCO 3.0.9. Therefore, the consequences
of an accident previously evaluated are not significantly affected by
this change. The addition of a requirement to assess and manage the
risk introduced by this change will further minimize possible concerns.
Therefore, this change does not involve a significant increase in the
probability or consequences of an accident previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident From any Previously Evaluated
The proposed change does not involve a physical alteration of the
plant (no new or different type of equipment will be installed).
Allowing delay times for entering supported system TS when
inoperability is due solely to an unavailable barrier, if risk is
assessed and managed, will not introduce new failure modes or effects
and will not, in the absence of other unrelated failures, lead to an
accident whose consequences exceed the consequences of accidents
previously evaluated. The addition of a requirement to assess and
manage the risk introduced by this change will further minimize
possible concerns. Thus, this change does not create the possibility of
a new or different kind of accident from an accident previously
evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed change allows a delay time for entering a supported
system TS when the inoperability is due solely to an unavailable
barrier, if risk is assessed and managed. The postulated initiating
events which may require a functional barrier are limited to those with
low frequencies of occurrence, and the overall TS system safety
function would still be available for the majority of anticipated
challenges. The risk impact of the proposed TS changes was assessed
following the three-tiered approach recommended in [NRC Regulatory
Guide (RG) 1.177, ``An Approach for Plant-Specific, Risk-Informed
Decisionmaking: Technical Specifications'']. A bounding risk assessment
was performed to justify the proposed TS changes. This application of
LCO 3.0.9 is predicated upon the licensee's performance of a risk
assessment and the management of plant risk. The net change to the
margin of safety is insignificant as indicated by the anticipated low
levels of associated risk (ICCDP [incremental conditional core damage
probability] and ICLERP [incremental conditional large early release
probability]) as shown in Table 1 of Section 3.1.1 in the Safety
Evaluation. Therefore, this change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the 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: Joseph A. Aluise, Associate General
Council--Nuclear, Entergy Services, Inc., 639 Loyola Avenue, New
Orleans, Louisiana 70113.
NRC Branch Chief: Michael T. Markley.
NextEra Energy Point Beach, LLC (NextEra, the Licensee), Docket Nos.
50-266 and 50-301, Point Beach Nuclear Plant, Units 1 and 2, Town of
Two Creeks, Manitowac County, Wisconsin
Date of amendment request: June 23, 2011.
Description of amendment request: The proposed amendment will
remove the Table of Contents from the Technical Specifications and
place it under licensee control. The Table of Contents (TOCs) for the
Technical Specifications (TSs) is not being eliminated. The
responsibility for maintenance and issuance of updates to the TOCs will
transfer from the U.S. Nuclear Regulatory Commission (NRC) to the
licensee. The TOCs will no longer be included in the TSs and, as such,
will no longer be part of Appendix A to the Operating License.
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 is administrative and affects control of
a document, the TOCs, listing the specifications in the plant TSs.
Transferring control from the NRC to NextEra does not affect the
operation, physical configuration, or function of plant equipment or
systems. The proposed amendment does not impact the initiators or
assumptions of analyzed events, nor does it impact the mitigation of
accidents or transient events.
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 is administrative and does not alter
plant configuration, require installation of new equipment, alter
assumptions about previously analyzed accidents, or impact operation
or function of plant equipment or systems.
Therefore, this 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 is administrative. The TOCs is not
required by regulation to be in the TSs. Removal does not impact any
safety assumptions or have the potential to reduce a margin of
safety. The proposed amendment involves a transfer of control of the
TOCs from the NRC to NextEra. No change in the technical content of
the TSs is involved. Consequently, transfer from the NRC to NextEra
has no impact on the margin of safety.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
[[Page 44618]]
amendment request involves no significant hazards consideration.
Attorney for licensee: William Blair, Senior Attorney, NextEra
Energy Point Beach, LLC, P.O. Box 14000, Juno Beach, FL 33408-0420.
NRC Branch Chief: Robert J. Pascarelli.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339,
North Anna Power Station, Unit 1 and 2, Louisa County, Virginia
Date of amendment request: July 19, 2010, as supplemented September
9, 2010, January 26, May 16, and June 23, 2011.
Description of amendment request: Changes are proposed to the
Technical Specifications to include an analytical methodology for the
critical heat flux correlation.
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 change involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
Approval of the proposed changes will allow Dominion to use the
VIPRE [Versatile Internals and Components Program for Reactors--
EPRI]-DIWRB-2M and VIPRE-DIW-3 code/correlation pairs to perform
licensing calculations of Westinghouse RFA-2 fuel in North Anna
Cores, using the DDLs [deterministic design limits] documented in
Appendix C of the DOM-NAF-2-A Fleet Report and the SDL [statistical
design limit] documented herein. Neither the code/correlation pair
nor the Statistical Departure from Nucleate Boiling Ratio (DNBR)
Evaluation Methodology affect accident initiators and thus cannot
increase the probability of any accident. Further, since both the
deterministic and statistical DNBR limits meet the required design
basis of avoiding Departure from Nucleate Boiling (DNB) with 95%
probability at a 95% confidence level, the use of the new code/
correlation and Statistical DNBR Evaluation Methodology do not
increase the potential consequences of any accident. Finally, the
full core DNB design limit provides increased assurance that the
consequences of a postulated accident which includes radioactive
release would be minimized because the overall number of rods in DNB
would not exceed the 0.1% level. The pertinent evaluations to be
performed as part of the cycle specific reload safety analysis to
confirm that the existing safety analyses remain applicable have
been performed and determined to be acceptable. The use of a
different code/correlation pair will not increase the probability of
an accident because plant systems will not be operated in a
different manner, and system interfaces will not change. The use of
the VIPRE-DIWRB-2M and VIPRE-DIW-3 code/correlation pairs to perform
licensing calculations of Westinghouse RFA-2 fuel in North Anna
cores will not result in a measurable impact on normal operating
plant releases and will not increase the predicted radiological
consequences of accidents postulated in the UFSAR [Updated Final
Safety Analysis Report].
Therefore, neither the probability of occurrence nor the
consequences of any accident previously evaluated is significantly
increased.
2. Does the change create the possibility of a new or different
kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not involve a physical alteration of
the plant (no new or different type of equipment will be installed).
The use of VIPRE-D/WRB-2M and the VIPRE-D/W-3 code/correlation pairs
and the applicable fuel design limits for DNBR does not impact any
of the applicable design criteria and the licensing basis criteria
will continue to be met. Demonstrated adherence to these standards
and criteria precludes new challenges to components and systems that
could introduce a new type of accident. Setpoint safety analysis
evaluations have demonstrated that the use of VIPRE-D/WRB-2M and
VIPRE-D/W3 is acceptable. Design and performance criteria will
continue to be met and no new single failure mechanisms will be
created. The use of the VIPRE-D/WRB-2M and VIPRE-D/W-3 code/
correlation pairs and the Statistical DNBR Evaluation Methodology
does not involve any alteration to plant equipment or procedures
that would introduce any new or unique operational modes or accident
precursors. Thus, this change does not create the possibility of a
new or different kind of accident from any accident previously
evaluated.
3. Does this change involve a significant reduction in a margin
of safety?
Response: No.
Approval of the proposed changes will allow Dominion to use the
VIPRE-D/WRB-2M and VIPRE-D/W-3 code/correlation pairs to perform
licensing calculations of Westinghouse RFA-2 fuel in North Anna
cores, using the DDLs documented in Appendix C of the DOM-NAF-2-A
Fleet Report and the SDL documented herein. The SDL has been
developed in accordance with the Statistical DNBR Evaluation
Methodology. North Anna TS 2.1, ``Safety Limits,'' specifies that
any DNBR limit established by any code/correlation must provide at
least 95% non-DNB probability at a 95% confidence level. The DNBR
limits meet the design basis of avoiding DNB with 95% probability at
a 95% confidence level. The required DNBR margin of safety for North
Anna Power Station, which in this case is the margin between the 95/
95 DNBR limit and clad failure, is therefore not reduced.
Therefore, the proposed TS change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion
Resources Services, Inc., 120 Tredegar Street, RS-2, Richmond, VA
23219.
NRC Branch Chief: Gloria Kulesa.
Previously Published Notices of Consideration of Issuance of Amendments
to Facility Operating 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.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Units 1, 2,
and 3, Maricopa County, Arizona
Date of amendment request: August 27, 2010, as supplemented by
letters dated February 11 and May 25, 2011.
Brief description of amendment request: The proposed amendment
would revise the feedwater line break with loss of offsite power and
single failure (FWLB/LOP/SF) analysis summarized in the Palo Verde
Nuclear Generating Station Updated Safety Analysis Report. The revision
would change the credited operator action to 20 minutes from 30 minutes
to control the pressurizer level. The revision would also revise the
rate of reactor coolant pump (RCP) bleed-off to the reactor drain tank
from three gallons per minute to zero.
Date of publication of individual notice in Federal Register: June
28, 2011 (76 FR 37853).
Expiration date of individual notice: July 28, 2011, for comments
and August 29, 2011, for hearings.
Notice of Issuance of Amendments to Facility Operating Licenses
During the period since publication of the last biweekly notice,
the
[[Page 44619]]
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.
Notice of Consideration of Issuance of Amendment to Facility
Operating License, Proposed No Significant Hazards Consideration
Determination, and Opportunity for A Hearing in connection with these
actions was published in the Federal Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) The
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection at
the NRC's Public Document Room (PDR), located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through the Agencywide Documents Access and
Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
PDR Reference staff at 1-800-397-4209, 301-415-4737 or by email to
[email protected].
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois; Docket Nos.
STN 50-454 and STN 50-455, Byron Station, Unit 1 and 2, Ogle County,
Illinois
Date of application for amendment: June 29, 2010, as supplemented
on August 24, 2010, and January 13, 2011.
Brief description of amendment: The license amendments revise
Technical Specifications (TS) Section 3.4.12, ``Low Temperature
Overpressure Protection (LTOP) System,'' to correct an inconsistency
between the TS, and implementation of procedures and administrative
controls for Safety Injection pumps required to mitigate a postulated
loss of decay heat removal during mid-loop operation as discussed in
NRC Generic Letter 88-17, ``Loss of Decay Heat Removal.''
Date of issuance: June 29, 2011.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment Nos.: 167, 167, 174, 174.
Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and NPF-66:
The amendments revise the TSs and license.
Date of initial notice in Federal Register: October 5, 2010 (75 FR
61526). The August 24, 2010, and January 13, 2011, 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 June 29, 2011.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 15th day of July 2011.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2011-18525 Filed 7-25-11; 8:45 am]
BILLING CODE 7590-01-P