[Federal Register Volume 76, Number 26 (Tuesday, February 8, 2011)]
[Notices]
[Pages 6830-6836]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-2743]
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NUCLEAR REGULATORY COMMISSION
[NRC-2011-0028]
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
[[Page 6831]]
Commission publish notice of any amendments issued, or proposed to be
issued and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license upon a
determination by the Commission that such amendment involves no
significant hazards consideration, notwithstanding the pendency before
the Commission of a request for a hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued from January 13, 2011 to January 26, 2011. The
last biweekly notice was published on January 25, 2011 (76 FR 4381).
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, Room O1-F21,
11555 Rockville Pike (first floor), Rockville, Maryland 20852-2738.
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, Room O1-F21,
11555 Rockville Pike (first floor), Rockville, Maryland 20852-2738.
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
[[Page 6832]]
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the Internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least
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 identification (ID) certificate, which allows the participant
(or its counsel or representative) to digitally sign documents and
access the E-Submittal server for any proceeding in which it is
participating; and (2) advise the Secretary that the participant will
be submitting a request or petition for hearing (even in instances in
which the participant, or its counsel or representative, already holds
an NRC-issued digital ID certificate). Based upon this information, the
Secretary will establish an electronic docket for the hearing in this
proceeding if the Secretary has not already established an electronic
docket.
Information about applying for a digital ID certificate is
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in NRC's ``Guidance for Electronic
Submission,'' which is available on the agency's public Web site at
http://www.nrc.gov/site-help/e-submittals.html. Participants may
attempt to use other software not listed on the Web site, but should
note that the NRC's E-Filing system does not support unlisted software,
and the NRC Meta System Help Desk will not be able to offer assistance
in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with NRC guidance
available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an e-mail notice confirming receipt of the document. The
E-Filing system also distributes an e-mail notice that provides access
to the document to the NRC Office of the General Counsel and any others
who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC Web site
at http://www.nrc.gov/site-help/e-submittals.html, by e-mail at
[email protected], or by a toll-free call at 1-866-672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland, 20852, Attention: Rulemaking and Adjudications Staff.
Participants filing a document in this manner are responsible for
serving the document on all other participants. Filing is considered
complete by first-class mail as of the time of deposit in the mail, or
by courier, express mail, or expedited delivery service upon depositing
the document with the provider of the service. A presiding officer,
having granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd1.nrc.gov/EHD/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information. With
respect to copyrighted works, except for limited excerpts that serve
the purpose of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Non-timely filings
will not be entertained absent a determination by the presiding officer
that the petition or request should be granted or the contentions
should be admitted, based on a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the Commission's PDR, located at One White Flint
North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville,
[[Page 6833]]
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
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].
Carolina Power & Light Company, Docket Nos. 50-325 and 50-324,
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North
Carolina.
Date of amendment request: September 13, 2010.
Description of amendment request: The proposed license amendments
would revise Brunswick Steam and Electric Plant, Units 1 and 2
Technical Specification (TS) 5.3.1, ``Facility Staff Qualifications.''
Specifically, TS 5.3.1 would be revised to be consistent with existing
TS 5.2.2.f regarding senior reactor operator (SRO) requirements for the
operations manager.
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 change to TS 5.3.1 corrects a discrepancy between TS 5.3.1
and TS 5.2.2.f regarding the operation manager SRO requirements.
This change is administrative in nature and does not affect the
qualification requirements for the operations manager which were
previously approved by the NRC. The proposed change does not
directly affect plant operations. The change does not physically
alter the facility in any manner and, as such, does not affect the
means in which any safety-related system performs its intended
safety function. Therefore, the proposed amendments do 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 license amendment does not create the possibility
of a new or different kind of accident from any accident previously
evaluated. As stated above, the proposed change is administrative in
nature. It does not involve physical alterations of the plant
configuration or changes in setpoints or operating parameters.
Therefore, there is no possibility of creating a new or different
kind of accident.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The change to TS 5.3.1 is administrative in nature, correcting a
discrepancy between TS 5.3.1 and TS 5.2.2.f regarding the operation
manager SRO requirements. As documented in the November 4, 1998,
safety evaluation for BSEP amendments 204 and 234 to the BSEP Unit 1
and 2 TSs, respectively, the requirements of TS 5.2.2.f: (1) ensure
that operations management maintains in-depth, plant-specific
knowledge and are consistent with the intent of ANSI-N18.1-1971, (2)
ensure that operations management can effectively interface with
day-to-day operational aspects of control room activities and can
communicate operational issues to higher levels of plant and utility
management, and (3) are consistent with 10 CFR 50.54(1), which
requires individuals responsible for directing the licensed
activities of licensed operators to hold an SRO license. Therefore,
the proposed amendments do not result in a significant reduction in
the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, NC 27602.
NRC Branch Chief: Douglas A. Broaddus.
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power
Station, Unit 1, DeWitt County, Illinois
Date of amendment request: October 8, 2010.
Description of amendment request: The proposed changes revise
Technical Specification (TS) 3.8.3, ``Diesel Fuel Oil, Lube Oil, and
Starting Air,'' by relocating the current stored diesel fuel oil and
lube oil numerical volume requirements from the TS to the TS Bases so
that they may be modified under licensee control. The TS are being
modified so that the stored diesel fuel oil and lube oil inventory will
require that a 7-day supply be available for each diesel generator.
Condition A and Condition B in the Action table are being revised and
Surveillance Requirements (SRs) 3.8.3.1 and 3.8.3.2 are being revised
to reflect the above change. In addition, the reference to Appendix B
of American National Standards Institute (ANSI) N195-1976, ``Fuel Oil
Systems for Standby Diesel Generators,'' in the TS Bases is deleted.
Instead, ANSI N195-1976 will be referenced. Reference to Appendix B of
ANSI N195-1976 in the TS Bases is not required. ANSI N195-1976 and
Regulatory Guide 1.137, Revision 1, ``Fuel-Oil Systems for Standby
Diesel Generators,'' are the current TS Bases 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. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change relocates the volume of diesel fuel oil and
lube oil required to support 7-day operation of the onsite diesel
generators, and the volume equivalent to a 6-day supply, to licensee
control. The specific volume of fuel oil equivalent to a 7- and 6-
day supply is calculated using the maximum post loss of coolant
accident load demands applied for the entire seven day and six day
periods. The specific volume of lube oil equivalent to a 7- and 6-
day supply is based on the diesel generator manufacturer's
consumption values for the run time of the diesel generator. Because
the requirement to maintain a 7-day supply of diesel fuel oil and
lube oil is not changed and is consistent with the assumptions in
the accident analyses, and the actions taken when the volume of fuel
oil and lube oil are less than a 6-day supply have not changed,
neither the probability nor the consequences of any accident
previously evaluated will be 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 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 any physical alteration of
the plant (i.e., no new or different type of equipment will be
installed), or a change in the methods governing normal plant
operation. The change does not alter assumptions made in the safety
analysis but ensures that the diesel generators operate as assumed
in the accident analysis. The proposed change is consistent with the
safety analysis assumptions. Therefore, the proposed change does not
create the possibility of a new or different kind of accident from
any accident previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed change relocates the volume of diesel fuel oil and
lube oil required to support 7-day operation of the onsite diesel
generators, and the volume equivalent to a 6-day supply, to licensee
control. As the bases for the existing limits on diesel fuel oil and
lube oil are not changed, no change is made
[[Page 6834]]
to the accident analysis assumptions and no margin of safety is
reduced as part of this change. 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: Mr. Bradley J. Fewell, Associate General
Counsel, Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555.
NRC Branch Chief: Robert D. Carlson.
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 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 20852-2738. 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].
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit 1, 2,
and 3, Maricopa County, Arizona
Date of application for amendment: April 29, 2010, as supplemented
by letter dated August 24, 2010.
Brief description of amendment: The amendments revised the
Technical Specifications (TSs) to incorporate Technical Specifications
Task Force (TSTF) change traveler TSTF-479-A, ``Changes to Reflect
Revision of 10 CFR 50.55a,'' as modified by TSTF-497-A, ``Limit
Inservice Testing Program SR [Surveillance Requirement] 3.0.2
Application to Frequencies of 2 Years or Less.'' Specifically, the
changes associated with TSTF-479-A replaced the reference in TS 5.5.8,
``Inservice Testing Program,'' to the American Society of Mechanical
Engineers (ASME) Boiler and Pressure Vessel Code with a reference to
the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM
Code) and specified that the extension allowance of SRs is applicable
to the frequencies in the Inservice Testing Program. The changes
associated with TSTF-497-A limited the applicability of SR 3.0.2 to
frequencies of 2 years or less. In addition, the amendment removed the
reference to component supports for consistency with the Standard
Technical Specifications because the supports are included in the
licensee's Inservice Inspection Program.
Date of issuance: January 19, 2011.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: Unit 1--184; Unit 2--184; Unit 3--184.
Facility Operating License Nos. NPF-41, NPF-51, and NPF-74: The
amendment revised the Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: July 27, 2010 (75 FR
44023). The supplemental letter dated August 24, 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.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 19, 2011.
No significant hazards consideration comments received: No.
Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of application for amendment: January 4, 2010, supplemented by
letter dated October 22, 2010.
Brief description of amendment: The amendment revises the core
spray flow requirement in the Technical specifications Surveillance
Requirements 3.5.1.8 and 3.5.2.6 from 6350 gallons per minute (gpm) to
5725 gpm (at a discharge head corresponding to a reactor pressure of
100 psig) consistent with the flow assumed in the Emergency Core
Cooling System safety analysis evaluations.
Date of issuance: January 24, 2011.
Effective date: As of the date of issuance and shall be implemented
within 60 days.
Amendment No.: 184.
Facility Operating License No. NPF-43: Amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: April 20, 2010 (75 FR
20631). The supplemental letters contained clarifying information and
did not change the initial no significant hazards consideration
determination, and did not expand the scope of the original
application.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 24, 2011.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point
Nuclear Generating Unit 3, Westchester County, New York
Date of application for amendment: November 19, 2009, as
supplemented on January 28 and December 16, 2010.
Brief description of amendment: The amendment revises the test
acceptance criteria specified in the Technical Specifications for the
emergency diesel generator endurance test surveillance.
Date of issuance: January 25, 2011.
Effective date: As of the date of issuance, and shall be
implemented within 120 days.
[[Page 6835]]
Amendment No.: 242.
Facility Operating License No. DPR-64: The amendment revised the
License and the Technical Specifications.
Date of initial notice in Federal Register: March 9, 2010 (75 FR
10829). The January 28 and December 16, 2010, supplements provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the NRC staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 25, 2011.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-293, Pilgrim Nuclear
Power Station, Plymouth County, Massachusetts
Date of application for amendment: January 24, 2010, as
supplemented by letters dated September 7 and November 4, 2010.
Brief description of amendment: This amendment request would revise
the Technical Specifications (TSs) Section 1.0, Definitions, TS Section
3.6, Primary System Boundary Specifications 3.6.A, and TS Programs and
Manuals Section 5.5, to include reference to the Pressure and
Temperature Limits Report (PTLR). The proposed PTLR would include
revised 43 effective full-power years pressure-temperature curves,
neutron fluence, and adjusted reference temperature values.
Date of issuance: January 26, 2011.
Effective date: As of the date of issuance, and shall be
implemented within 60 days.
Amendment No.: 234.
Facility Operating License No. DPR-35: The amendment revised the
License and Technical Specifications.
Date of initial notice in Federal Register: April 6, 2010 (75 FR
17443). The supplemental letters dated September 7 and November 4,
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.
The Commission's related evaluation of this amendment is contained
in a Safety Evaluation dated January 26, 2011.
No significant hazards consideration comments received: No.
Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo
Canyon Nuclear Power Plant, Unit 1 and 2, San Luis Obispo County,
California
Date of application for amendments: July 3, 2009, as supplemented
by letters dated April 9 and July 22, 2010.
Brief description of amendments: The amendments revised Technical
Specification (TS) 3.4.15, ``RCS [Reactor Coolant System] Leakage
Detection Instrumentation.'' Specifically, the amendments added a new
Condition D for any inoperable containment sump monitor, the
containment atmosphere particulate radioactivity monitor, and the
containment fan cooler unit (CFCU) condensate collection monitor, and
revised TS 3.4.15 Condition A, Required Action A.2, Condition B,
Required Action B.2 and the associated TS Bases. The amendment request
is consistent with Technical Specification Task Force (TSTF) Traveler
TSTF-513, ``Revise PWR [Pressurized-Water Reactor] Operability
Requirements and Actions for RCS Leakage Instrumentation,'' with the
exception of Condition E. To be consistent with the final version of
TSTF-513 published in the Federal Register on January 3, 2011 (76 FR
189), as part of the consolidated line item improvement process, the
NRC staff has denied the proposed change to TS 3.4.15 Condition E. The
basis for the removal of Condition E from the TSTF is discussed in
TSTF-513, Revision 3 (Agencywide Documents Access and Management System
(ADAMS) Accession No. ML102360355).
Date of issuance: January 24, 2011.
Effective date: As of its date of issuance and shall be implemented
within 180 days from the date of issuance.
Amendment Nos.: Unit 1-209; Unit 2-211.
Facility Operating License Nos. DPR-80 and DPR-82: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: August 25, 2009 (74 FR
42928). The supplemental letters dated April 9 and July 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.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 24, 2011.
No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Inc., Georgia Power Company,
Oglethorpe Power Corporation, Municipal Electric Authority of Georgia,
City of Dalton, Georgia, Docket Nos. 50-424 and 50-425, Vogtle Electric
Generating Plant, Units 1 and 2, Burke County, Georgia
Date of application for amendments: June 15, 2010, as supplemented
on January 7, 2011.
Brief description of amendments: The amendments relocate specific
surveillance frequency requirements to a licensee controlled program
using the Technical Specification Task Force (TSTF) recommendation 425-
A Revision 3.
Date of issuance: January 19, 2011.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment Nos.: 158 and 140.
Renewed Facility Operating License Nos. NPF-68 and NPF-81:
Amendments revised the licenses and the technical specifications.
Date of initial notice in Federal Register: August 24, 2010 (75 FR
52042).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 19, 2011.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339,
North Anna Power Station, Units 1 and 2, Louisa County, Virginia
Date of application for amendment: January 29, 2010.
Brief description of amendment: The amendments revised an Emergency
Action Level (EAL) scheme based on NUREG-0654, ``Criteria for
Preparation and Evaluation of Radiological Emergency Response Plan and
Preparedness in Support of Nuclear Power Plants,'' to one based on
Nuclear Energy Institute (NEI) 99-01, ``Methodology for Development of
Emergency Action Levels,'' Revision 4. This would change the
methodology for deriving selected Notification of Unusual Event values
in Table R-1, Gaseous Effluent Monitor Classification Thresholds, and
deleting EAL RA2.4 which evaluates abnormal radiation readings at
infrequently accessed areas and revise the radiation level threshold
values for reactor coolant system (RCS) letdown indication.
Date of issuance: January 26, 2011.
Effective date: As of the date of issuance and shall be implemented
[[Page 6836]]
within 120 days from the date of issuance.
Amendment Nos.: 261 and 242.
Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments
revised the licenses.
Date of initial notice in Federal Register: April 6, 2010 (75 FR
17447).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 26, 2011.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, et al., Docket Nos. 50-280 and 50-
281, Surry Power Station, Units 1 and 2, Surry County, Virginia
Date of application for amendments: January 29, 2010.
Brief Description of amendments: These amendments revised an
Emergency Action Level (EAL) scheme based on NUREG-0654, ``Criteria for
Preparation and Evaluation of Radiological Emergency Response Plan and
Preparedness in Support of Nuclear Power Plants,'' to one based on
Nuclear Energy Institute (NEI) 99-01, ``Methodology for Development of
Emergency Action Levels,'' Revision 4. This would change the
methodology for deriving selected Notification of Unusual Event values
in Table R-1, Gaseous Effluent Monitor Classification Thresholds, and
deleting EAL RA2.4 which evaluates abnormal radiation readings at
infrequently accessed areas.
Date of issuance: January 26, 2011.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment Nos.: 272 and 271.
Renewed Facility Operating License Nos. DPR-32 and DPR-37:
Amendments revised the licenses.
Date of initial notice in Federal Register: April 6, 2010 (75 FR
17448).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 26, 2011.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland this 28th day of January 2011.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2011-2743 Filed 2-7-11; 8:45 am]
BILLING CODE 7590-01-P