[Federal Register Volume 77, Number 179 (Friday, September 14, 2012)]
[Notices]
[Pages 56877-56883]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2012-22698]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0213]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (NRC or the
Commission) 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 August 23 to September 5, 2012. The last
biweekly notice was published on September 4, 2012 (77 FR 53923).
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and are publicly available,
by searching on http://www.regulations.gov under Docket ID NRC-2012-
0213. You may submit comments by any of the following methods:
Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0213. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: [email protected].
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:
[[Page 56878]]
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2012-0213 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 http://www.regulations.gov and search for Docket ID NRC-2012-0213.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. Documents may be viewed in
ADAMS by performing a search on the document date and docket number.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2012-0213 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 http://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 section 50.92 of Title 10 of the Code
of Federal Regulations (10 CFR), this means that operation of the
facility in accordance with the proposed amendment would not (1)
involve a significant increase in the probability or consequences of an
accident previously evaluated; or (2) create the possibility of a new
or different kind of accident from any accident previously evaluated;
or (3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Within 60 days after the date of publication of this notice, any
person(s) whose interest may be affected by this action may file a
request for a hearing and a petition to intervene with respect to
issuance of the amendment to the subject facility operating license or
combined license. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ``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's regulations are accessible electronically from the NRC
Library on the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to
intervene is filed by the above date, the Commission or a presiding
officer designated by the Commission or by the Chief Administrative
Judge of the Atomic Safety and Licensing Board Panel, will rule on the
request and/or petition; and the Secretary or the Chief Administrative
Judge of the Atomic Safety and Licensing Board will issue a notice of a
hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include
[[Page 56879]]
sufficient information to show that a genuine dispute exists with the
applicant on a material issue of law or fact. Contentions shall be
limited to matters within the scope of the amendment under
consideration. The contention must be one which, if proven, would
entitle the requestor/petitioner to relief. A requestor/petitioner who
fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in the NRC adjudicatory proceedings, including
a request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139;
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at http://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with the NRC guidance
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC Web site
at http://www.nrc.gov/site-help/e-submittals.html, by email 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 the
NRC's electronic hearing docket which is
[[Page 56880]]
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. Requests for hearing,
petitions for leave to intervene, and motions for leave to file new or
amended contentions that are filed after the 60-day deadline will not
be entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the following three
factors in 10 CFR 2.309(c)(1): (i) The information upon which the
filing is based was not previously available; (ii) the information upon
which the filing is based is materially different from information
previously available; and (iii) the filing has been submitted in a
timely fashion based on the availability of the subsequent information.
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. Publicly available documents created or received at the NRC are
accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC's PDR Reference staff at 1-800-397-4209,
301-415-4737, or by email to [email protected].
Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point
Nuclear Generating Unit 3, Westchester County, New York
Date of amendment request: May 23, 2012, as supplemented by letter
dated August 3, 2012.
Description of amendment request: The proposed amendment will
revise Technical Specification 3.7.4, ``Atmospheric Dump Valves
(ADVs),'' limiting condition for operation (LCO) to require four rather
than three ADVs to be operable. The licensee states that the current
LCO is non-conservative and is being addressed in accordance with
Administrative Letter 98-10.
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. The NRC staff has reviewed the licensee's analysis
against the standards of 10 CFR 50.92(c). The NRC staff's review 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 current LCO requires three atmospheric dump valves to be
operable. The proposed change would be an administrative change to
require that all four atmospheric dump valves be operable during the
applicable operating modes.
Operating experience has demonstrated that ADVs are significant
to public health and safety. ADVs are not the initiators of any
accident because a failed open ADV can be isolated with a block
valve. ADVs are available to cool the unit to residual heat removal
entry conditions should the preferred heat sink via the steam bypass
system to the condenser not be available. ADVs are also available to
limit the releases during a steam generator tube rupture accident.
Therefore the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the change create the possibility of a new or different
kind of accident from any accident previously evaluated?
Response: No.
There are no changes to design, no changes to operating
procedures and the revised LCO is consistent with the normal
operating condition. Also, the ADVs are not the initiators of any
accident because a failed open ADV can be isolated with a block
valve.
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 is administrative in nature. Revising the
LCO to require all four ADVs to be operable during the applicable
operating modes adds conservatism to the technical specifications
and does not reduce any margin of safety.
Therefore the proposed change does not involve a significant
reduction in a margin of safety.
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., 440 Hamilton Avenue, White
Plains, NY 10601.
NRC Branch Chief: George Wilson.
Northern States Power Company--Minnesota, Docket No. 50-306, Prairie
Island Nuclear Generating Plant, Unit 2, Goodhue County, Minnesota
Date of amendment request: July 25, 2012.
Description of amendment request: The proposed amendment would
revise Appendix A of the Operating License to except Prairie Island
Nuclear Generating Plant, Unit 2 from the requirements of Regulatory
Guide 1.163, as specified in Technical Specification 5.5.14,
``Containment Leakage Rate Testing Program,'' for post-modification
containment leak rate testing associated with steam generator
replacement.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change would provide the Prairie Island Nuclear
Generating Plant an exception from performing a containment
integrated leak rate test following the replacement of the steam
generators in Unit 2.
Integrated leak rate tests are performed to assure the leak-
tightness of the primary containment boundary system, and as such
they are not accident initiators. Therefore, not performing an
integrated leak rate test will not affect the probability of an
accident previously evaluated.
The intent of post-modification integrated leak rate testing
requirements is to assure the leak-tight integrity of the area
affected by the modification. For the Unit 2 steam generator
replacement modification, this intent will be satisfied by
performing the inspections and tests required by the American
Society of Mechanical Engineers (ASME) Code. Because the leak-
tightness integrity of the primary containment boundary affected by
the steam generator replacement will be assured, there is no change
in the primary containment boundary's ability to confine radioactive
materials during an accident.
Therefore, adding a Technical Specification statement that
provides an exception for Unit 2 from the steam generator
replacement post-modification integrated leak rate testing
requirements does not involve a significant increase in the
probability or consequences of an accident previously evaluated.
2. Do the proposed changes create the possibility of a new or
different kind of
[[Page 56881]]
accident from any accident previously evaluated?
Response: No.
The proposed change would provide the Prairie Island Nuclear
Generating Plant an exception from performing a required containment
integrated leak rate test following the replacement of the steam
generators in Unit 2.
Providing an exception from performing a test does not involve a
physical change to the plant nor does it change the operation of the
plant. Thus, it cannot introduce a new failure mode. Therefore,
adding a Technical Specification statement that provides an
exception for Unit 2 from the steam generator replacement post-
modification integrated leak rate testing requirements does not
create the possibility of a new or different kind of accident from
any previously evaluated.
3. Do the proposed changes involve a significant reduction in a
margin of safety?
Response: No.
The proposed change would provide the Prairie Island Nuclear
Generating Plant an exception from performing a required containment
integrated leak rate test following the replacement of the steam
generators in Unit 2.
The intent of post-modification integrated leak rate testing
requirements is to assure the leak-tight integrity of the area
affected by the modification. This intent will be satisfied by
performing inspections and tests required by the ASME Code. The
acceptance criterion for ASME Code system pressure testing for the
base metal and welds is no leakage. In addition, the test pressure
for the hydrostatic tests and the inservice system pressure test
will be several times that required during an integrated leak rate
test. Because the leak-tight integrity of the primary containment
boundary affected by the steam generator replacement will be
assured, there is no change in the primary containment boundary's
ability to confine radioactive materials during an accident.
Therefore, adding a Technical Specification statement that provides
an exception for Unit 2 from the steam generator replacement post
modification integrated leak rate testing requirements does not
involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment requests involve no significant hazards consideration.
Attorney for licensee: Peter M. Glass, Assistant General Counsel,
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
NRC Acting Branch Chief: Istvan Frankl.
Northern States Power Company--Minnesota, Docket Nos.: 50-282 and 50-
306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue
County, Minnesota
Date of amendment request: July 25, 2012.
Description of amendment request: The proposed amendments would
revise Technical Specifications (TS) 3.4.19--``Steam Generator (SG)
Tube Integrity,'' 5.5.8--``Steam Generator (SG) Program,'' and 5.6.7--
``Steam Generator Tube Inspection Report'' to apply the appropriate
program attributes to the Unit 2 replacement steam generators that are
planned for installation in fall 2013. The proposed amendment would
also revise the same TS described above to adopt for Unit 1 and Unit 2
the program improvements in Technical Specifications Task Force
Traveler (TSTF) 510, Revision 2, ``Revision to Steam Generator Program
Inspection Frequencies and Tube Sample Selection.''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes associated with Technical Specification
Task Force Traveler (TSTF) 510 revise the Steam Generator (SG)
Program to modify the frequency of verification of SG tube integrity
and SG tube sample selection. A steam generator tube rupture (SGTR)
event is one of the design basis accidents that are analyzed as part
of a plant's licensing basis. The proposed SG tube inspection
frequency and sample selection criteria will continue to ensure that
the SG tubes are inspected such that the probability of a SGTR is
not increased. The consequences of a SGTR are bounded by the
conservative assumptions in the design basis accident analysis. The
proposed change will not cause the consequences of a SGTR to exceed
those assumptions.
The proposed changes associated with Unit 2 SG replacement
preserve the intent of the PlNGP TS for the new plant configuration
following Unit 2 steam generator replacement. In effect, these
changes will eliminate the SG tube repair criteria that were only
applicable to the original SGs that will be replaced. These changes
will ensure that the Unit 2 replacement SGs are subject to the
inservice inspection, testing, and reporting criteria that are
applicable to their design as approved for use with TSTF-510.
Therefore, it is concluded that this change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
2. Do the proposed changes create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes to the Steam Generator Program associated
with TSTF-510 will not introduce any adverse changes to the plant
design basis or postulated accidents resulting from potential tube
degradation. The proposed change does not affect the design of the
SGs or their method of operation. In addition, the proposed change
does not impact any other plant system or component.
The proposed changes associated with Unit 2 SG replacement
preserve the intent of the PlNGP TS for the new plant configuration
following Unit 2 steam generator replacement. In effect, these
changes will eliminate the SG tube repair criteria that were only
applicable to the original SGs that will be replaced. Such
programmatic changes do not affect the design of the SGs or their
method of operation. In addition, these programmatic changes do not
impact any other plant system or component.
Therefore, it is concluded that this change does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Do the proposed changes involve a significant reduction in a
margin of safety?
Response: No.
The SG tubes in pressurized water reactors are an integral part
of the reactor coolant pressure boundary and, as such, are relied
upon to maintain the primary system's pressure and inventory. As
part of the reactor coolant pressure boundary, the SG tubes are
unique in that they are also relied upon as a heat transfer surface
between the primary and secondary systems such that residual heat
can be removed from the primary system. In addition, the SG tubes
also isolate the radioactive fission products in the primary coolant
from the secondary system. In summary, the safety function of a SG
is maintained by ensuring the integrity of its tubes.
Steam generator tube integrity is a function of the design,
environment, and the physical condition of the tube. The proposed
changes do not affect tube design or operating environment. The
proposed changes will continue to require monitoring of the physical
condition of the SG tubes such that there will not be a reduction in
the margin of safety compared to the current requirements.
Therefore, it is concluded that the proposed change does not
involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment requests involve no significant hazards consideration.
Attorney for licensee: Peter M. Glass, Assistant General Counsel,
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
[[Page 56882]]
NRC Acting Branch Chief: Istvan Frankl.
Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant
(WBN), Unit 1, Rhea County, Tennessee
Date of amendment request: June 13, 2012.
Description of amendment request: The proposed amendment would
selectively implement an Alternate Source Term (AST) methodology in
accordance with Regulatory Position C.1.2.2 of Regulatory Guide (RG)
1.183, ``Alternative Radiological Source Terms for Evaluating Design
Basis Accidents at Nuclear Power Reactors,'' by modifying the WBN, Unit
1 licensing basis for determining offsite and Control Room doses due to
a Fuel Handling Accident (FHA). A license amendment is required for AST
implementation in accordance with 10 CFR 50.67(b)(1).
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 consequence of an accident previously evaluated?
Response: No.
The equipment affected by the proposed changes is mitigative in
nature, and relied upon after an accident has been initiated.
Application of the AST does not involve any physical changes to the
plant design. While the operation of various systems will change as
a result of these proposed changes, these systems are not accident
initiators. Application of the AST is not an initiator of a design
basis accident. The proposed changes to the TS [technical
specifications], while they revise certain performance requirements,
do not involve any physical modifications to the plant. As a result,
the proposed changes do not affect any of the parameters or
conditions that could contribute to the initiation of any accidents.
As such, removal of operability requirements during the specified
conditions will not significantly increase the probability of
occurrence for an accident previously analyzed. Since design basis
accident initiators are not being altered by adoption of the AST
analysis of the FHA, the probability of an accident previously
evaluated is not affected.
The dose consequences of a FHA have been re-evaluated utilizing
the AST methodology recognized by 10 CFR 50.67 and the guidance
contained within Regulatory Guide 1.183. Based upon the results of
this analysis, TVA has demonstrated that, with the requested
changes, the dose consequences of the FHA are within the appropriate
acceptance criteria of 10 CFR 50.67(b)(2) and Table 6 of RG 1.183.
The AST involves quantities, isotopic composition, chemical and
physical characteristics, and release timing of radioactive material
for use as inputs to the dose analysis of the FHA. Selective
implementation of the AST does not create any conditions that could
significantly increase the consequences of any of the events being
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 amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes would not require any new or different
accidents to be postulated, since no changes are being made to the
plant that would introduce any new accident causal mechanisms. This
license amendment request does not impact any plant systems that are
potential accident initiators. The AST methodology involves
quantities, isotopic composition, chemical and physical
characteristics, and release timing of radioactive material for use
as inputs to the dose analysis of the FHA.
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.
TVA is proposing to modify the methodology for responding to a
FHA. Selective implementation of the AST methodology is relevant
only to the calculated dose consequences for the FHA. The
radiological analysis of the FHA does not credit containment
isolation, operation of the Auxiliary Building Gas Treatment System,
or operation of the Reactor Building Purge Air Cleanup Units. The
results of the revised dose consequences analysis demonstrate that
the regulatory acceptance criteria regarding onsite and offsite
doses are met for the FHA.
In addition, the selective implementation of the AST methodology
does not affect the transient behavior of non-radiological
parameters (e.g., RCS [reactor coolant system] pressure, Containment
pressure) that are pertinent to a margin of safety.
Therefore, the proposed amendment does not involve a significant
reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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: General Counsel, Tennessee Valley Authority,
400 West Summit Hill Drive, ET 11A, Knoxville, Tennessee 37902.
NRC Branch Chief: George Wilson.
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental 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 Commission's Public Document Room (PDR), located at One White Flint
North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville,
Maryland 20852. Publicly available documents created or received at the
NRC are accessible electronically through the Agencywide Documents
Access and Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS
or if there are problems in accessing the documents located in ADAMS,
contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by
email to [email protected].
[[Page 56883]]
Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of application for amendment: December 20, 2011.
Brief description of amendment: The amendment revised technical
specifications (TS) requirements related to primary containment
isolation instrumentation. The changes are in accordance with NRC
approved TS Task Force (TSTF), Improved Standard Technical
Specifications (ISTS) change TSTF-306, Revision 2.
Date of issuance: August 29, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment No.: 189.
Facility Operating License No. NPF-43: Amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: April 3, 2012 (77 FR
20073).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 29, 2012.
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket No. 50-315, Donald C. Cook
Nuclear Plant, Unit 1, Berrien County, Michigan
Date of application for amendment: September 29, 2011, as
supplemented on July 25, 2012.
Brief description of amendment: The amendment revised Technical
Specification (TS) 4.2.1, adding Optimized ZIRLO\TM\ clad fuel rods to
the fuel matrix in addition to Zircaloy or ZIRLO\TM\ clad fuel rods
that are currently in use. The amendment also added a Westinghouse
topical report regarding Optimized ZIRLO\TM\ as Reference 8 in TS
5.6.5.b, which lists the analytical methods used to determine the core
operating limits.
Date of issuance: August 23, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days from the date of issuance.
Amendment No.: 302.
Facility Operating License No. DPR-58: Amendment revised the
Renewed Operating License and Technical Specifications.
Date of initial notice in Federal Register: November 29, 2011 (76
FR 73731). The licensee's July 25, 2012, supplemental letter contained
clarifying information, did not change the scope of the original
license amendment request, did not change the NRC staff's initial
proposed finding of no significant hazards consideration determination,
and did not expand the scope of the original Federal Register notice.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 23, 2012.
No significant hazards consideration comments received: No.
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold
Energy Center, Linn County, Iowa
Date of application for amendments: September 29, 2011, as
supplemented by letter dated March 12, 2012.
Brief description of amendments: The amendment modified existing
Technical Specification Surveillance Requirement (SR) 3.4.3.2, SR
3.5.1.9, and SR 3.6.1.5.1, to provide an alternate means for testing of
the steam safety/relief valves (SRVs). The change allows for
demonstrating the capability of the SRVs to perform their function
without requiring the valves to be cycled with steam pressure while
installed in the plant in accordance with the Inservice Testing
Program.
Date of issuance: August 27, 2012.
Effective date: This license amendment is effective as of the date
of issuance and shall be implemented within 30 days from date of
issuance.
Amendment No.: 282.
Renewed Facility Operating License No. DPR-49: Amendment revised
the Renewed Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: June 12, 2012 (77 FR
35075).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 27, 2012.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota (NSPM), Docket No. 50-263,
Monticello Nuclear Generating Plant, Wright County, Minnesota
Date of application for amendment: May 25, 2012.
Brief description of amendment: The amendment revised the
Monticello licensing basis, approving the removal of automatic transfer
capability of essential electrical buses to the 1AR transformer due to
degraded voltage conditions.
Date of issuance: August 27, 2012.
Effective date: This license amendment is effective as of the date
of its issuance, and shall be implemented within 30 days of issuance,
except the revision of the updated safety analysis report to reflect
the revised licensing basis of the 1AR transformer shall follow the
schedule set forth in 10 CFR 50.71(e).
Amendment No.: 169.
Facility Operating License No. DPR-22. Amendment revised the
Renewed Facility Operating License.
Date of initial notice in Federal Register: June 26, 2012 (77 FR
38096).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 27, 2012.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 6th day of September 2012.
For the Nuclear Regulatory Commission.
Louise Lund,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2012-22698 Filed 9-13-12; 8:45 am]
BILLING CODE 7590-01-P