[Federal Register Volume 75, Number 104 (Tuesday, June 1, 2010)]
[Notices]
[Pages 30440-30451]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-12888]
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NUCLEAR REGULATORY COMMISSION
[NRC-2010-0192]
Biweekly Notice: Applications and Amendments to Facility
Operating Licenses Involving No Significant Hazards Considerations
I. 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
[[Page 30441]]
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 May 6 to May 19, 2010. The last biweekly
notice was published on May 18, 2010 (75 FR 27825).
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 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.
Written comments may be submitted by mail to the Chief, Rules,
Announcements, and Directives Branch (RADB), TWB-05-B01M, Division of
Administrative Services, Office of Administration, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, and should cite the
publication date and page number of this Federal Register notice.
Written comments may also be faxed to the RADB at 301-492-3446.
Documents may be examined, and/or copied for a fee, at the NRC's Public
Document Room (PDR), located at One White Flint North, Public File Area
O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
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 Commission's PDR, located at One White Flint North, Public File
Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Publicly available records will be accessible from the Agencywide
Documents Access and Management System's (ADAMS) Public Electronic
Reading Room on the Internet at the NRC Web site, 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, any hearing held
would take place before the issuance of any amendment.
[[Page 30442]]
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
ten (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 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 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 EIE, 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 (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://ehd.nrc.gov/EHD_Proceeding/home.asp, 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 Commission's PDR, located at One White Flint
North, Public File Area O1F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible from
the ADAMS Public Electronic Reading Room on the Internet at the NRC Web
site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have
[[Page 30443]]
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].
Calvert Cliffs Nuclear Power Plant, LLC, Docket Nos. 50-317 and 50-318,
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County,
Maryland
Date of amendment requests: April 5, 2010.
Description of amendments request: The amendment would make title
changes and corrections within Technical Specification (TS) 5.0,
``Administrative Controls.'' Specifically, the proposed changes would
include:
(1) Replacement of the use of plant-specific titles to generic
titles consistent with TS Task Force (TSTF) Traveler TSTF-65, Revision
1, ``Use of Generic Titles for Utility Positions,''
(2) Changes made to more closely align selected TSs with the
Improved Standard TSs, and
(3) Administrative changes to specified TSs.
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?
No.
The first portion of the proposed change, involving adoption of
a generic title vice a plant specific personnel title, is
administrative in nature. As such, this change does not involve any
change to the design basis of the plant or of any structure, system,
or component. As a result there is no change to the probability or
consequences of any previously evaluated accident.
The second portion of the proposed change involves changes to
Technical Specifications that align them to the words used in the
Improved Standard Technical Specifications for gaseous effluents to
include effluents that are already routinely monitored. In addition,
the proposed change in requiring either the operations manager or
assistant operations manager to hold a Senior Reactor Operator (SRO)
license meets the established standards of American National
Standards Institute N18.1-1971 for individuals filling the
applicable positions. These changes do not involve any change to the
design basis of the plant or of any structure, system, or component.
As a result there is no change to the probability or consequences of
any previously evaluated accident.
The third portion of the proposed change involves administrative
changes that do not involve any change to the design basis of the
plant or of any structure, system, or component. As a result there
is no change to the probability or consequences of any previously
evaluated accident.
Therefore, operation of the facility in accordance with the
proposed changes will not involve a significant increase in the
probability or consequence 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?
No.
The first portion of the proposed change, involving adoption of
a generic title vice a plant specific personnel title is
administrative in nature. As such, this change does not result in
any physical alterations to the plant configuration, make any change
to plant operation, or alter any design function. As a result no new
accident failure mechanisms or single failures are introduced.
The second portion of the proposed change involves changes to
Technical Specifications that align those Technical Specifications
to the words used in the Improved Standard Technical Specifications
for gaseous effluent monitoring to include certain effluents that
are already routinely monitored. In addition, the proposed change
requiring either the operations manager or assistant operations
manager to hold an SRO license meets the established standards of
American National Standards Institute N18.1-1971 for individuals
filling the applicable positions. These changes do not involve any
change to the design basis of the plant or of any structure, system,
or component. As a result no new accident failure mechanisms or
single failures are introduced.
The third portion of the proposed change involves administrative
changes that do not involve any change to the design basis of the
plant or of any structure, system, or component. As a result no new
accident failure mechanisms or single failures are introduced.
Therefore, operation of the facility in accordance with the
proposed changes will not involve a significant increase in the
probability or consequence of an accident previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
No.
The first portion of the proposed change, involving adoption of
a generic title vice a plant specific personnel title is
administrative in nature. As such, this change involves no change to
the design bases functions or to the controlling values of
parameters used to avoid exceeding regulatory or licensing limits.
As a result there is no decrease in any margin of safety due to this
proposed change.
The second portion of the proposed change involves changes to
Technical Specifications that align those Technical Specifications
to the words used in the Improved Standard Technical Specifications
for gaseous effluent monitoring to include certain effluents that
are already routinely monitored. In addition, the proposed change
requiring either the operations manager or assistant operations
manager to hold an SRO license meets the established standards of
American National Standards Institute N18.1-1971 for individuals
filling the applicable positions. As such, these changes involve no
change to the design bases functions or to the controlling values of
parameters used to avoid exceeding regulatory or licensing limits.
As a result there is no decrease in any margin of safety due to
these proposed changes.
The third portion of the proposed change involves administrative
changes that do not involve any change to the design basis of the
plant or of any structure, system, or component. As such, these
changes involve no change to the design bases functions or to the
controlling values of parameters used to avoid exceeding regulatory
or licensing limits. As a result there is no decrease in any margin
of safety due to these proposed changes.
Therefore, operation of the facility in accordance with the
proposed changes will 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
amendments request involves no significant hazards consideration.
Attorney for licensee: Carey Fleming, Sr. Counsel--Nuclear
Generation, Constellation Generation Group, LLC, 750 East Pratt Street,
17th floor, Baltimore, MD 21202.
NRC Branch Chief: Nancy L. Salgado.
Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson
Steam Electric Plant, Unit No. 2, Darlington County, South Carolina
Date of amendment request: March 5, 2010.
Description of amendment request: The proposed change would revise
H. B. Robinson Steam Electric Plant's Technical Specifications (TS)
Section 3.3.2, ``Engineered Safety Feature Actuation System (ESFAS)
Instrumentation,'' to allow the performance of maintenance activities
for an inoperable containment pressure-high high channel. The proposed
change to TS 3.3.6, ``Containment Ventilation Isolation
Instrumentation,'' corrects an error related to table references.
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. The Proposed Change Does Not Involve a Significant Increase
in the Probability or Consequences of an Accident Previously
Evaluated.
[[Page 30444]]
The proposed changes to TS 3.3.2 are intended to allow for the
performance of maintenance activities required to return an
inoperable channel to service with the instrumentation and plant in
a condition that reduces the probability of an inadvertent transient
or the need for a plant shutdown. Therefore, the proposed change
reduces the probability of an accident because the likelihood of
accident initiation is decreased.
The emergency safety features that are actuated by the
Containment Pressure-High High channels are Main Steam Line
Isolation, Containment Spray, and Containment Phase B isolation.
These safety features are intended to reduce the consequences of
design basis accident scenarios. These safety features are still
expected to function as designed. Actuation from containment
pressure exceeding the High High trip setpoint will still occur with
one trip signal bypassed based on the input from the other five
channels. Should an additional failure result in the inability to
actuate based on Containment Pressure-High High, there are other
means to actuate these safety features in a timely manner. Main
Steam Line Isolation based on High High containment pressure is only
important for the assumed main steam line break inside containment.
For such an accident, main steam line isolation will still
automatically occur from either High Steam Flow in Two Steam Lines
Coincident with Tavg-Low, or High Steam Flow in Two Steam
Lines Coincident with Steam Line Pressure-Low. In regard to
Containment Spray and Containment Phase B Isolation, the operator
can manually initiate these functions if automatic actuation did not
occur and containment conditions warranted actuation. Therefore,
there will not be a significant increase in the consequences of
analyzed accidents.
The proposed change to TS 3.3.6 is an administrative correction
and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the
proposed amendment would not involve a significant increase in the
probability or consequences of an accident previously evaluated.
2. The Proposed Change Does Not Create the Possibility of a New
or Different Kind of Accident From Any Previously Evaluated.
As described above, the proposed change to TS 3.3.2 would allow
a single Containment Pressure-High High channel to not be in the
trip condition for maintenance purposes for a limited period of time
(up to six hours). This is a condition that is already allowed
during the first six hours of the action statement.
Therefore, no new accident initiators or precursors are
introduced by the proposed change.
The proposed change to TS 3.3.6 is an administrative correction
and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the
proposed amendment would not create the possibility of a new or
different kind of accident from any previously evaluated.
3. The Proposed Change Does Not Involve a Significant Reduction
in the Margin of Safety.
As described above, the proposed change to TS 3.3.2 would allow
a single Containment Pressure-High High channel to not be in the
trip condition for a limited period of time (up to six hours) to
allow an effective means of maintenance to return an inoperable
channel to service. It is expected that safety systems will continue
to function as designed with a single channel not in trip and
therefore there will be no impact on the accident analyses or a
reduction in the margin of safety.
The proposed change to TS 3.3.6 is an administrative correction
and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the
proposed amendment would 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: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, North Carolina 27602.
NRC Acting Branch Chief: Douglas A. Broaddus.
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 amendment request: September 3, 2009.
Description of amendment request: The amendments would revise the
Technical Specification (TS) Section 3.7.10, ``Control Room Area
Ventilation System (CRAVS),'' to allow movement of irradiated fuel with
only one CRAVS train OPERABLE.
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?
The proposed changes do not adversely affect accident initiators
or precursors nor alter the design assumptions, conditions, or
configurations of the facility. The proposed changes do not alter or
prevent the ability of structure, systems and components (SSCS) to
perform their intended function to mitigate the consequences of an
initiating event within the assumed acceptance limits. This is a
revision to the TS for the control room ventilation system which is
a mitigation system designed to minimize unfiltered air inleakage
into the control room and to filter the Control Room atmosphere to
protect occupants following an accident previously analyzed. The
Control Room ventilation system is not an initiator or precursor to
any accident previously evaluated. Therefore, the probability or
consequences of any accident previously evaluated are not increased.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
This revision will not impact the accident analysis. The change
will not alter the requirements of the Control Room ventilation
system or its function during accident conditions. No new or
different accidents result from the changes proposed. The changes do
not involve a physical alteration of the plant (i.e., no new or
different type of equipment will be installed) or significant
changes in methods governing normal plant operation. The changes do
not alter assumptions made in the safety analysis. The proposed
changes are consistent with the safety analyses assumptions.
Therefore, it is concluded that these changes do not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed change involve a significant reduction in
margin of safety?
The proposed changes do not alter the manner in which safety
limits, limiting safety system settings or limiting conditions for
operations are determined. The safety analysis acceptance criteria
are not affected by these changes. The proposed changes will not
result in plant operation in a configuration outside the design
basis for an acceptable period of time without compensatory
measures. The proposed changes do not adversely affect systems that
respond to safely shutdown the plant and to maintain the plant in a
safe shutdown condition. It is therefore concluded that the proposed
changes do 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: Ms. Lisa F. Vaughn, Associate General
Counsel and Managing Attorney, Duke Energy Carolinas, LLC, 526 South
Church Street, EC07H, Charlotte, NC 28202.
NRC Branch Chief: Gloria Kulesa.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: March 29, 2010.
Description of amendment request: The proposed change revises the
[[Page 30445]]
Technical Specifications (TSs) to delete channel check surveillance
requirements in TS 3.3.6.1, ``Primary Containment Isolation
Instrumentation,'' for the traversing in-core probe (TIP) isolation
instrumentation.
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 revises TS 3.3.6.1 by eliminating a channel
check SR [surveillance requirement]. The controls and requirements
of TS[s] otherwise continue to be enforced. The proposed change does
not affect any plant equipment, test methods, or plant operation,
and does not affect the initiation of any analyzed accident
sequence. The allowance to un-isolate a penetration flow path is
preserved and will not have a significant effect on the mitigation
of any accident previously evaluated because the penetration flow
path can be isolated, if needed, by a dedicated operator. The option
to isolate a TIP penetration continues to be preserved and ensures
the penetration will perform as assumed in the accident analysis.
Operation in accordance with the proposed TS will ensure that all
analyzed accidents will continue to be mitigated as previously
analyzed.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not involve a physical alteration to
the plant (i.e., no new or different type of equipment will be
installed) or a change to the methods governing normal plant
operation. The changes do not alter the assumptions made in the
safety analysis.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed 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 un-isolate a penetration flow path will
not have a significant effect on a margin of safety because the
penetration flow path can be isolated manually, if needed. The
option to isolate a TIP penetration is preserved, and will continue
to ensure the penetration will perform as assumed in the accident
analysis.
Therefore, the proposed changes do 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: William A. Horin, Esq., Winston & Strawn,
1700 K Street, NW., Washington, DC 20006-3817.
NRC Branch Chief: Michael T. Markley.
Energy Northwest, Docket No. 50-397, Columbia Generating Station,
Benton County, Washington
Date of amendment request: March 31, 2010.
Description of amendment request: The proposed change revises the
Technical Specifications (TSs) to add a channel check surveillance
requirement to TS 3.3.6.1, ``Primary Containment Isolation
Instrumentation,'' for the reactor pressure vessel low water level
isolation signal to the primary containment isolation valves.
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.
Adding a channel check surveillance for the main steam low water
level isolation function does not increase the probability or
consequences of a previously evaluated accident. The proposed change
does not impact the logic or performance of the isolation function.
The proposed change increases assurance that the isolation function
will be operable by providing increased monitoring.
Therefore the proposed change does not increase probability or
consequences for an evaluated accident.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
No modifications are being made under the proposed change that
create the possibility of a new or different kind of accident.
Overall system reliability is improved due to more frequent
monitoring.
Therefore the proposed change does not create the possibility of
new or different accidents.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The addition of a channel check surveillance provides increased
assurance of operability of the MSIV [main steam isolation valve]
low water level isolation function.
Therefore the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: William A. Horin, Esq., Winston & Strawn,
1700 K Street, NW., Washington, DC 20006-3817.
NRC Branch Chief: Michael T. Markley.
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power
Station, Unit No.1, DeWitt County, Illinois
Date of amendment request: April 2, 2010.
Description of amendment request: The proposed amendment would
revise the Exelon Nuclear Radiological Emergency Plan Annex for Clinton
Power Station (CPS), Unit No. 1, Table B-1, ``Minimum Staffing
Requirements for the On-Shift Clinton Station [Emergency Response
Organization] ERO,'' to increase the Non-Licensed Operator (NLO)
staffing from two to four, allow in-plant protective actions to be
performed by personnel assigned to other functions, and replace a
Mechanical Maintenance person with a NLO.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes to the CPS Emergency Plan Table B-1,
``Minimum Staffing Requirements for the On-Shift Clinton Station
ERO,'' were evaluated against plant operations during design basis
accidents, Radiation Protection (RP) personnel tasks associated with
design basis accidents, and the CPS radiological accident
assessment. The reallocation of functions between ERO responders and
the addition of two NLOs does not reduce the minimum number of on-
shift staffing, nor does it reduce or impede the tasks that are
required to be performed during an emergency event. This change does
not reduce the functionality of tasks required to be
[[Page 30446]]
performed; therefore, since all personnel will be trained and
qualified to perform all assigned tasks, this change does not reduce
the effectiveness of the ERO's performance or the CPS Emergency Plan
in mitigating the consequences of any accident.
The probability of a reactor accident requiring implementation
of the CPS Emergency Plan has no relevance in determining whether
the proposed change reduces the effectiveness of the CPS Emergency
Plan. The Planning Basis section of NUREG-0654, Revision 1,
``Criteria for Preparation and Evaluation of Radiological Emergency
Response Plans and Preparedness in Support of Nuclear Power
Plants,'' describes how to address the likelihood of an event during
the development of an emergency response plan. According to NUREG-
0654, Revision 1:
The overall objective of emergency response plans is to provide
dose savings (and in some cases immediate life saving) for a
spectrum of accidents that could produce offsite doses in excess of
Protective Action Guides (PAGs). No single specific accident
sequence should be isolated as the one for which to plan because
each accident could have different consequences, both in nature and
degree. Further, the range of possible selection for a planning
basis is very large, starting with a zero point of requiring no
planning at all because significant offsite radiological accident
consequences are unlikely to occur, to planning for the worst
possible accident, regardless of its extremely low likelihood.
Therefore, while the proposed changes will not impact the
probability or consequences of any previously evaluated accident,
[Exelon Generation Company, LLC] EGC did not consider the risk
insights regarding any specific accident initiation or progression
in evaluating the proposed change.
Process improvements made by CPS associated with the activation
of the ERO will ensure emergency responders will be available on-
site in the allotted timeframe. Additionally, CPS successfully
demonstrated the capability to fully staff and activate the ERO
facilities in a September 16, 2004, off-hours augmentation drive-in
drill. This drill confirmed that the CPS ERO is capable of being
staffed, with the proposed staffing, in the allotted amount of time.
The proposed changes do not adversely affect accident initiators
or precursors nor alter the design assumptions, conditions, and
configuration, or the manner in which the plant is operated and
maintained. The proposed changes do not adversely affect the ability
of structures, systems, or components (SSCs) to perform their
intended safety functions in mitigating the consequences of an
initiating event within the assumed acceptance limits.
The proposed changes do not affect the source term, containment
isolation, or radiological release assumptions used in evaluating
the radiological consequences of any accident previously evaluated.
Further, since the changes are simply a reallocation of
responsibilities from one group of trained and qualified individuals
to another, the proposed changes do not increase the types and
amounts of radioactive effluent that may be released off site, nor
significantly increase individual or cumulative occupational or
public radiation exposures.
Therefore, the probability of an accident is not impacted, nor
is there a significant impact on the consequences of an accident
previously evaluated, introduced by the proposed changes.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes do not involve the addition or modification
of any plant equipment. Moreover, the proposed changes will not
alter the design configuration, or method of operation of plant
equipment beyond its normal functional capabilities. CPS ERO
functions will continue to be performed as required. The proposed
modification of ERO assignments does not create any new credible
failure mechanisms, malfunctions, or accident initiators.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from those that have been
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed changes do not alter or exceed a design basis
parameter or safety limit for any system or component. No change to
the setpoint or environmental condition of any SSC or the manner in
which any SSC is operated is proposed. The proposed changes do not
affect any of the assumptions used in any accident analysis, nor do
they affect any operability requirement for equipment important to
plant safety. The requirements of 10 CFR 50.47, ``Emergency plans,''
paragraph (b) and 10 CFR 50, Appendix E, ``Emergency Planning and
Preparedness for Production and Utilization Facilities,'' will
continue to be met.
Therefore, the proposed changes do not involve any reduction in
a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. Bradley J. Fewell, Associate General
Counsel, Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555.
NRC Branch Chief: Stephen J. Campbell.
PSEG Nuclear LLC, Docket No. 50-311, Salem Nuclear Generating Station,
Unit No. 2, Salem County, New Jersey
Date of amendment request: March 29, 2010.
Description of amendment request: The proposed amendment would
revise the Technical Specifications (TSs) to allow a one-time
replacement of the 2C 125-volt direct current (VDC) battery while Salem
Unit 2 is at power.
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.
During the replacement of the existing 2C 125VDC battery, a
temporary, TS operable battery will provide the same function as the
battery being removed. The temporary battery has been analyzed to
comply with the required design functions of the existing 2C 125VDC
battery. The temporary battery will be subjected to all required TS
surveillance testing prior to being utilized to confirm operability.
The temporary battery will be placed in service during the current
TS AOT [allowed outage time]. The respective DC bus will be
continuously energized by the existing battery charger.
Consequently, the structures, systems, and components (SSCs) of the
plant will continue to perform their design function. The proposed
change will have no adverse affect on plant operations, or any
design function or analysis.
The proposed change does not affect accident initiators or
precursors, or design assumptions for the systems or components used
to mitigate the consequences of an accident as analyzed in the UFSAR
[Updated Final Safety Analysis Report]. The temporary battery will
be operable while the permanent 2C 125VDC battery is replaced and
the other divisions of DC power will also remain operable to support
design mitigation capability.
Therefore, the proposed changes do not represent 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.
During the replacement of the existing 2C 125VDC battery, a
temporary battery will provide the same function as the 2C 125VDC
battery that is being replaced. This temporary battery possesses
adequate capacity to fulfill the safety-related requirements of
supplying necessary power to the associated 125VDC bus. Because the
temporary battery will perform like the station battery that is
currently installed, no new electrical or functional failure modes
are created. Equipment will be operated in the same manner that is
currently allowed and designed for. Consequently, there is no change
to the design function or operation of the SSCs involved and no
possibility of a new or different kind of accident due to credible
new failure mechanisms, malfunctions, or accident initiators not
previously considered in the design and licensing bases.
The proposed one-time change does not introduce any new accident
initiators or
[[Page 30447]]
precursors or any new design assumptions for those systems or
components used to mitigate the consequences of an accident.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
During the replacement of the 2C 125VDC battery, a TS operable
125VDC battery will temporarily perform the same function. The
temporary replacement 125VDC battery will be assembled from the same
type and manufactured safety-related Class 1E cells. The temporary
replacement 125VDC battery will meet all the design requirements as
the 2C 125VDC battery that it replaces. It will possess adequate
capacity to fulfill the requirements of the associated 125VDC bus.
The proposed replacement activity will not prevent the plant from
mitigating a Design Basis Accident (DBA) during the time the
temporary battery is in service. Required DC power systems
supporting the design mitigation capability will be maintained. The
associated DC bus will always be supplied by either the temporary
battery and/or the battery charger at all times. The proposed change
does not alter a design basis or safety limit; therefore it does not
significantly reduce the margin of safety. The 2C 125VDC bus will
continue to operate per the existing design and regulatory
requirements.
Therefore, this proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Vincent Zabielski, PSEG Nuclear LLC--N21,
P.O. Box 236, Hancocks Bridge, NJ 08038.
NRC Branch Chief: Harold K. Chernoff.
Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant,
Unit 1, Rhea County, Tennessee
Date of amendment request: February 24, 2010.
Description of amendment request: The proposed amendment would
revise Technical Specification (TS) 3.7.11 ``Control Room Emergency Air
Temperature Control System (CREATCS).'' The proposed change would only
be applicable during plant modifications to upgrade the CREATCS
chillers. This ``one-time'' TS change would be implemented during Watts
Bar Nuclear Plant, Unit 1 Cycles 10 and 11 beginning December 1, 2010,
and ending January 29, 2012.
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 Control Room Emergency Air Treatment System (CREATCS) is
used to maintain an acceptable environment for control room
personnel and equipment during normal and emergency conditions. The
proposed ``one-time'' Technical Specification (TS) to extend the
Completion Time for loss of one train from 30 days to 60 days is
justified because the additional risk of operating the plant beyond
the current Completion Time of 30 days is compensated by the
addition of a temporary, non-safety related cooling system with a
diesel generator backup.
The CREATCS system does not have the potential to create a
design basis accident as it only provides MCRHZ [main control room
habitability zone] cooling and do not directly mitigate postulated
accidents. Temporary cooling equipment will be designed in
accordance with appropriate design controls, sized to ensure
adequate cooling capacity, and located such that safety-related
features would not be prevented from performing their safety
function. Since the MCR chillers do not contribute to the initiators
of postulated accidents, the probability of an accident is not
significantly increased by the proposed change.
The MCR HVAC [heating, ventilation, and air conditioning]
Systems do ensure a suitable environment for safety-related
equipment and personnel during an accident. The temperature limits
placed on the temporary cooling system ensure that the control room
areas will remain at acceptable levels to support plant evolutions
in response to postulated accidents. Safety functions that are
necessary to maintain acceptable offsite dose limits will not be
degraded by the proposed change. Alternate cooling methods that will
maintain the control room areas well within the equipment
temperature limits will ensure these safety functions. With the
control room cooling requirements satisfied, the offsite dose limits
are not affected.
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 ``one-time'' Completion Time extension will
continue to ensure that the control room ambient temperatures will
not exceed 90[deg]F. The temperature control functions for the
control room are not postulated to create an accident and since the
proposed change continues to maintain acceptable temperatures, no
new accident initiators are created.
Implementation of temporary cooling methods will be designed
such that safety-related features will not be prevented from
performing their safety functions and will be in compliance with 10
CFR 50.59 requirements. Plant operation during the use of such
alternate cooling methods will continue to comply with applicable
Technical Specification (TS) requirements. Therefore, the proposed
change does not create the possibility of a new or different kind of
accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed ``one-time'' Completion Time extension will
continue to maintain control room temperatures at acceptable levels
to ensure the availability of equipment necessary for safety
functions. Sufficient margin to temperature limits will be
maintained to ensure response to accident conditions can be managed
adequately and temperatures will remain at acceptable levels to
complete necessary accident mitigation actions. Plant components and
their setpoints will not be altered by the proposed change that
would impact the ability to respond to accident conditions. The
installation of temporary cooling devices will be designed such that
safety-related features would not be prevented from performing their
safety function. Therefore, the proposed change 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: L. Raghavan.
Notice of Issuance of Amendments to Facility Operating 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.
Notice of Consideration of Issuance of Amendment to Facility
Operating License, Proposed No Significant Hazards Consideration
Determination, and Opportunity for A Hearing in
[[Page 30448]]
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, Public File Area 01F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible from
the Agencywide Documents Access and Management System (ADAMS) Public
Electronic Reading Room on the internet at the NRC Web site, 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 e-mail to [email protected].
Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson
Steam Electric Plant, Unit No. 2, Darlington County, South Carolina
Date of application for amendment: December 16, 2009, as
supplemented by letters dated March 11, 2010, and April 22, 2010.
Brief description of amendment: The amendment revises Technical
Specification (TS) 5.5.9, ``Steam Generator (SG) Program,'' to allow
inspection of the steam generator tubes to start within the tubesheet
region (a minimum of 17.28 inches below the top of the tubesheet). The
amendment also adds requirements in TS 5.6.8, ``Steam Generator Tube
Inspection Report,'' to report indications in this region and primary
to secondary leakage that could be attributed to the uninspected
portion of the tube within the tubesheet. These changes are only
applicable until the end of Operating Cycle 27.
The supplements dated March 11, 2010, and April 22, 2010, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register on February 10, 2010
(75 FR 6731).
Date of issuance: May 7, 2010.
Effective date: Effective as of the date of issuance and shall be
implemented by the end of Refueling Outage 26.
Amendment No.: 224.
Renewed Facility Operating License No. DPR-23: The amendment
revises the technical specifications.
Date of initial notice in Federal Register: February 10, 2010 (75
FR 6731).
The Commission's related evaluation of the amendment is contained
in a safety evaluation dated May 7, 2010.
Public comments received as to proposed no significant hazards
consideration (NSHC): No.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station,
Unit No. 1, Washington County, Nebraska
Date of amendment request: May 29, 2009.
Brief description of amendment: The amendment modified the
Technical Specifications (TSs) as follows: (1) Revised the definition
for Operable-Operability; (2) modified the provisions under which
equipment may be considered operable when either its normal or
emergency power source is inoperable; (3) deleted TS limiting condition
for operation (LCO) 2.0.1(2); (4) deleted diesel generator Surveillance
Requirement 3.7.1(e); and (5) relocated the guidance for inoperable
power supplies and verifying the operability of redundant components
into the LCO for electrical equipment 2.7, ``Electrical Systems.''
Date of issuance: May 14, 2010.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment No.: 264.
Renewed Facility Operating License No. DPR-40: The amendment
revised the Technical Specifications.
Date of initial notice in Federal Register: October 6, 2009 (74 FR
51331).
The Commission's related evaluation of the amendment is contained
in a safety evaluation dated May 14, 2010.
No significant hazards consideration comments received: No.
Notice of Issuance of Amendments to Facility Operating Licenses and
Final Determination of No Significant Hazards Consideration and
Opportunity for a Hearing (Exigent Public Announcement or Emergency
Circumstances)
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 for the
amendment 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.
Because of exigent or emergency circumstances associated with the
date the amendment was needed, there was not time for the Commission to
publish, for public comment before issuance, its usual Notice of
Consideration of Issuance of Amendment, Proposed No Significant Hazards
Consideration Determination, and Opportunity for a Hearing.
For exigent circumstances, the Commission has either issued a
Federal Register notice providing opportunity for public comment or has
used local media to provide notice to the public in the area
surrounding a licensee's facility of the licensee's application and of
the Commission's proposed determination of no significant hazards
consideration. The Commission has provided a reasonable opportunity for
the public to comment, using its best efforts to make available to the
public means of communication for the public to respond quickly, and in
the case of telephone comments, the comments have been recorded or
transcribed as appropriate and the licensee has been informed of the
public comments.
In circumstances where failure to act in a timely way would have
resulted, for example, in derating or shutdown of a nuclear power plant
or in prevention of either resumption of operation or of increase in
power output up to the plant's licensed power level, the Commission may
not have had an opportunity to provide for public comment on its no
significant hazards consideration determination. In such case, the
license amendment has been issued without opportunity for comment. If
there has been some time for public comment but less than 30 days, the
Commission may provide an
[[Page 30449]]
opportunity for public comment. If comments have been requested, it is
so stated. In either event, the State has been consulted by telephone
whenever possible.
Under its regulations, the Commission may issue and make an
amendment immediately effective, notwithstanding the pendency before it
of a request for a hearing from any person, in advance of the holding
and completion of any required hearing, where it has determined that no
significant hazards consideration is involved.
The Commission has applied the standards of 10 CFR 50.92 and has
made a final determination that the amendment involves no significant
hazards consideration. The basis for this determination is contained in
the documents related to this action. Accordingly, the amendments have
been issued and made effective 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 51.12(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
application for amendment, (2) the amendment to Facility Operating
License, 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, Public File Area 01F21,
11555 Rockville Pike (first floor), Rockville, Maryland. Publicly
available records will be accessible from the Agencywide Documents
Access and Management System's (ADAMS) Public Electronic Reading Room
on the Internet at the NRC Web site, 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 e-mail to
[email protected].
The Commission is also offering an opportunity for a hearing with
respect to the issuance of the amendment. 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 Commission's PDR, located at One White Flint
North, Public File Area 01F21, 11555 Rockville Pike (first floor),
Rockville, Maryland, and electronically on the Internet at the NRC Web
site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are
problems in accessing the document, contact the PDR Reference staff at
1 (800) 397-4209, (301) 415-4737, or by e-mail to [email protected].
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 petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to those specific sources and
documents of which the petitioner is aware and on which the 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.\1\ 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 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.
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\1\ To the extent that the applications contain attachments and
supporting documents that are not publicly available because they
are asserted to contain safeguards or proprietary information,
petitioners desiring access to this information should contact the
applicant or applicant's counsel and discuss the need for a
protective order.
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Each contention shall be given a separate numeric or alpha
designation within one of the following groups:
1. Technical--primarily concerns/issues relating to technical and/
or health and safety matters discussed or referenced in the
applications.
2. Environmental--primarily concerns/issues relating to matters
discussed or referenced in the environmental analysis for the
applications.
3. Miscellaneous--does not fall into one of the categories outlined
above.
As specified in 10 CFR 2.309, if two or more petitioners/requestors
seek to co-sponsor a contention, the petitioners/requestors shall
jointly designate a representative who shall have the authority to act
for the petitioners/requestors with respect to that contention. If a
requestor/petitioner seeks to adopt the contention of another
sponsoring requestor/petitioner, the requestor/petitioner who seeks to
adopt the contention must either agree that the sponsoring requestor/
petitioner shall act as the representative with respect to that
contention, or jointly designate with the sponsoring requestor/
petitioner a representative who shall have the authority to act for the
petitioners/requestors with respect to that contention.
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. Since the Commission has made a final determination that the
amendment involves no significant hazards consideration, if a hearing
is requested, it will not stay the
[[Page 30450]]
effectiveness of the amendment. Any hearing held would take place while
the amendment is in effect.
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
ten (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 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 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 EIE, 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 (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://ehd.nrc.gov/EHD_Proceeding/home.asp, 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.
Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of amendment request: May 14, 2010.
Description of amendment request: The amendment extends the
Completion Time for Technical Specification 3.7.3 ``Control Room
Emergency Filtration (CREF) System,'' Condition B, from 24 hours to 48
hours on a one-time basis to support emergent repairs to the Division 2
Return Air Fan.
Date of issuance: May 15, 2010.
Effective date: As of the date of issuance and shall be implemented
within 1 day.
Amendment No.: 182.
[[Page 30451]]
Facility Operating License No. NPF-43: Amendment revises the
technical specifications and the operating license.
Public comments requested as to proposed no significant hazards
consideration (NSHC): No.
The Commission's related evaluation of the amendment, finding of
emergency circumstances, state consultation, and final NSHC
determination are contained in a safety evaluation dated May 15, 2010.
Attorney for licensee: David G. Pettinari, Attorney--Corporate
Matters, One Energy Plaza, Detroit, MI 48226.
NRC Branch Chief: Terry A. Beltz (Acting).
Dated at Rockville, Maryland, this 24th day of May 2010.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2010-12888 Filed 5-28-10; 8:45 am]
BILLING CODE 7590-01-P