[Federal Register Volume 76, Number 85 (Tuesday, May 3, 2011)]
[Notices]
[Pages 24926-24933]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-10405]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0095]


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 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 April 7, 2011, to April 20, 2011. The last 
biweekly notice was published on April 19, 2011 (76 FR 21917 to 21928).

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.
    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. Publicly 
available records will be accessible from the Agencywide Documents 
Access and Management System's (ADAMS) Public NRC Library 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/

[[Page 24927]]

petitioner seeks to have litigated at the proceeding.
    Each contention must consist of a specific statement of the issue 
of law or fact to be raised or controverted. In addition, the 
requestor/petitioner shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing. 
The requestor/petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
requestor/petitioner intends to rely to establish those facts or expert 
opinion. The petition must include sufficient information to show that 
a genuine dispute exists with the applicant on a material issue of law 
or fact. Contentions shall be limited to matters within the scope of 
the amendment under consideration. The contention must be one which, if 
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at 
least one contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing.
    If a hearing is requested, the Commission will make a final 
determination on the issue of no significant hazards consideration. The 
final determination will serve to decide when the hearing is held. If 
the final determination is that the amendment request involves no 
significant hazards consideration, the Commission may issue the 
amendment and make it immediately effective, notwithstanding the 
request for a hearing. Any hearing held would take place after issuance 
of the amendment. If the final determination is that the amendment 
request involves a significant hazards consideration, then any hearing 
held would take place before the issuance of any amendment.
    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing, a petition for leave to intervene, any motion or 
other document filed in the proceeding prior to the submission of a 
request for hearing or petition to intervene, and documents filed by 
interested governmental entities participating under 10 CFR 2.315(c), 
must be filed in accordance with the NRC E-Filing rule (72 FR 49139, 
August 28, 2007). The E-Filing process requires participants to submit 
and serve all adjudicatory documents over the internet, or in some 
cases to mail copies on electronic storage media. Participants may not 
submit paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 
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 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 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

[[Page 24928]]

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, 
Maryland 20852. Publicly available records will be accessible from the 
ADAMS Public NRC Library 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].

Entergy Operations, Inc., System Energy Resources, Inc., South 
Mississippi Electric Power Association, and Entergy Mississippi, Inc., 
Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne 
County, Mississippi

    Date of amendment request: April 6, 2011.
    Description of amendment request: The proposed amendment would 
revise the Technical Specification (TSs) to define a new time limit for 
restoring inoperable reactor coolant system (RCS) leakage detection 
instrumentation to operable status; establish alternate methods of 
monitoring RCS leakage when one or more required monitors are 
inoperable; and make TS Bases changes which reflect the proposed 
changes and more accurately reflect the contents of the facility design 
basis related to operability of the RCS leakage detection 
instrumentation. These changes are consistent with NRC-approved 
Revision 3 to TSTF Standard Technical Specification Change Traveler 
TSTF-514, ``Revise BWR Operability Requirements and Actions for RCS 
Leakage Instrumentation,'' as part of the consolidated line item 
improvement process. In addition, the proposed amendment would make a 
minor editorial change to correct a formatting issue to be consistent 
with the Technical Specifications Task Force TSTF-GG-05-01, ``Writer's 
Guide for Plant Specific Improved Technical Specifications,'' and the 
BWR6 TS format.
    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 clarifies the operability requirements for 
the RCS leakage detection instrumentation and reduces the time 
allowed for the plant to operate when the only TS-required operable 
RCS leakage detection instrumentation monitor is the drywell 
atmospheric gaseous radiation monitor. The monitoring of RCS leakage 
is not a precursor to any accident previously evaluated. The 
monitoring of RCS leakage is not used to mitigate the consequences 
of any accident previously evaluated.
    Therefore, it is concluded that this change does not involve a 
significant increase in the probability of 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 clarifies the operability requirements for 
the RCS leakage detection instrumentation and reduces the time 
allowed for the plant to operate when the only TS-required operable 
RCS leakage detection instrumentation monitor is the drywell 
atmospheric gaseous radiation monitor. The proposed change does not 
involve a physical alteration of the plant (no new or different type 
of equipment will be installed) or a change in the methods governing 
normal plant operation.
    Therefore, it is concluded that 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.
    The proposed change clarifies the operability requirements for 
the RCS leakage detection instrumentation and reduces the time 
allowed for the plant to operate when the only TS-required operable 
RCS leakage detection instrumentation monitor is the drywell 
atmospheric gaseous radiation monitor. Reducing the amount of time 
the plant is allowed to operate with only the drywell atmospheric 
gaseous radiation monitor operable increase the margin of safety by 
increasing the likelihood that an increase in RCS leakage will be 
detected before it potentially results in gross failure.
    Therefore, it is concluded that the proposed change does not 
involve a significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Terence A. Burke, Associate General 
Counsel--Nuclear Entergy Services, Inc., 1340 Echelon Parkway, Jackson, 
Mississippi 39213.
    NRC Branch Chief: Michael T. Markley.

Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island 
Nuclear Station, Unit 1, Dauphin County, Pennsylvania

    Date of amendment request: September 22, 2010, as supplemented by 
letter dated April 7, 2011.
    Description of amendment request: This notice is being reissued in 
its entirety due to a modified submittal received from Exelon 
Generation Company, LLC. The original notice was published in the 
Federal Register on November 30, 2010 (75 FR 74095). The proposed 
amendment would relocate the list of pumps, fans, and valves in 
Technical Specification (TS) 4.5.1.1b,

[[Page 24929]]

Sequence and Power Transfer Test, to the Three Mile Island, Unit 1 
(TMI-1) Updated Final Safety Analysis Report. In place of the TS 
equipment listing there will be a more general reference to the 
permanently-connected and automatically-connected emergency loads which 
are tested through the load sequencer. In addition, TS 4.5.1.2b, TS 
4.5.2.2a, and TS 4.5.2.2b refer to this test and are proposed for 
revision to reflect the proposed change to TS 4.5.1.1b.
    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 license amendment does not add, delete or modify 
plant equipment. The proposed changes are administrative in nature. 
The proposed amendment would relocate the list of pumps, fans and 
valves in Technical Specification (TS) 4.5.1.lb, Sequence and Power 
Transfer Test, to the TMI-1 Updated Final Safety Analysis Report 
(UFSAR) Section 8.2, Table 8.2-11, Engineered Safeguards Loading 
Sequence. In addition, TS 4.5.1.1b and TS 4.5.1.2b are being 
modified to include a high level description of equipment required 
to be included in the Sequence and Power Transfer Test, and the 
Sequence Test, respectively.
    The proposed changes relocate surveillance requirement details 
that are not required by 10 CFR 50.36. The proposed changes do not 
change current surveillance requirements. The subject list of pumps, 
fans and valves that will be relocated to UFSAR Section 8.2, Table 
8.2-11, will be controlled under 10 CFR 50.59.
    The probability of an accident is not increased by these 
proposed changes because neither the Sequence and Power Transfer 
Test nor the Sequence Test are initiators of any design basis event. 
Additionally, the proposed changes do not involve any physical 
changes to plant structures, systems, or components (SSCs), or the 
manner in which these SSCs are operated, maintained, or controlled. 
The consequences of an accident will not be increased because the 
proposed administrative changes to the Sequence and Power Transfer 
Test, and the Sequence Test, will continue to provide a high degree 
of assurance that the Electric Power System will meet its safety 
related function.
    Therefore, the proposed changes do 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 previously evaluated?
    Response: No.
    The proposed changes do not alter the physical design, safety 
limits, safety analyses assumptions, or the manner in which the 
plant is operated or tested. The proposed changes are administrative 
in nature and the surveillance requirements remain the same. 
Accordingly, the proposed changes do not introduce any new accident 
initiators, nor do they reduce or adversely affect the capabilities 
of any plant SSC in the performance of their safety function.
    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 amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The margin of safety is associated with the confidence in the 
ability of the fission product barriers (i.e., fuel cladding, 
reactor coolant pressure boundary, and containment structure) to 
limit the level of radiation to the public. There are no physical 
changes to SSCs or operating and testing procedures associated with 
the proposed amendment.
    The proposed changes do not impact the assumptions of any design 
basis accident, and do not alter assumptions relative to the 
mitigation of an accident or transient event. The proposed changes 
are administrative in nature and the surveillance requirements 
remain the same.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, 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: J. Bradley Fewell, Esquire, Associate 
General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, 
Warrenville, IL 60555.
    NRC Branch Chief: Harold K. Chernoff.

PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, 
Salem County, New Jersey

    Date of amendment request: February 28, 2011.
    Description of amendment request: The proposed amendment would 
modify the Hope Creek Generating Station (HCGS) Technical 
Specifications (TSs) to revise the existing TS for the Control Room 
Emergency Filtration (CREF) system and to add a new TS for the Control 
Room Air Conditioning (AC) system. The proposed amendment is based, in 
part, on Nuclear Regulatory Commission (NRC)-approved Technical 
Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-
477, Revision 3, ``Adding an Action Statement for Two Inoperable 
Control Room Air Conditioning Subsystems.'' Plant-specific deviations 
from TSTF-477 are proposed to accommodate differences between the HCGS 
TSs and the STSs originally used to develop TSTF-477.
    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 add a separate Technical Specification (TS) 
for the Control Room Air Conditioning (AC) system, and renumbers and 
revises the existing TS for the Control Room Emergency Filtration 
(CREF) system. Consistent with Technical Specification Task Force 
(TSTF) Standard TS Change Traveler TSTF-477, the proposed change 
also adds an action statement for two inoperable Control Room AC 
subsystems.
    The proposed change does not involve a physical alteration of 
the plant (no new or different type of equipment will be installed). 
The proposed changes add a separate TS for the Control Room AC 
system and an action statement for two inoperable control room 
subsystems. The equipment qualification temperature of the control 
room equipment is not affected. Future changes to the Bases or 
licensee-controlled document[s] will be evaluated pursuant to the 
requirements of 10 CFR 50.59, ``Changes, test and experiments,'' to 
ensure that such changes do not result in more than a minimal 
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, and 
configuration of the facility or the manner in which the plant is 
operated and maintained. The proposed changes do not adversely 
affect the ability of structures, systems and components (SSCs) to 
perform their intended safety function to mitigate the consequences 
of an initiating event within the assumed acceptance limits. The 
proposed changes do not affect the source term, containment 
isolation, or radiological consequences of any accident previously 
evaluated. Further, the proposed changes do not increase the types 
and the amounts of radioactive effluent that may be released, nor 
significantly increase individual or cumulative occupation/public 
radiation exposures.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed changes add a separate TS for the Control Room AC 
system and an

[[Page 24930]]

action statement for two inoperable control room subsystems. The 
changes do not involve a physical altering of the plant (i.e., no 
new or different type of equipment will be installed) or a change in 
methods governing normal plant control room temperature within the 
design limits.
    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 changes add a separate TS for the Control Room AC 
system and an action statement for two inoperable control room 
subsystems. Instituting the proposed changes will continue to 
maintain the control room temperature within design limits. Changes 
to the Bases or license[e-]controlled document[s] are performed in 
accordance with 10 CFR 50.59. This approach provides an effective 
level of regulatory control and ensures that the control room 
temperature will be maintained within design limits.
    The proposed changes maintain sufficient controls to preserve 
the current margins of safety.
    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: Jeffrie J. Keenan, PSEG Nuclear LLC--N21, 
P.O. Box 236, Hancocks Bridge, NJ 08038.
    NRC Branch Chief: Harold K. Chernoff.

Tennessee Valley Authority, Docket Nos. 50-260 and 50-296, Browns Ferry 
Nuclear Plant (BFN), Units 2 and 3, Limestone County, Alabama

    Date of amendment request: February 25, 2011.
    Description of amendment request: The proposed amendments would 
delete Technical Specification (TS) Surveillance Requirement 3.5.1.12, 
which requires the verification of the capability to automatically 
transfer the power supply from the normal source to the alternate 
source for each Low Pressure Coolant Injection (LPCI) subsystem inboard 
injection valve and each recirculation pump discharge valve on a 24-
month frequency.
    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 Technical Specification change involve a 
significant increase in the probability or consequences of an 
accident previously evaluated?
    Response: No.
    The 480V RMOV Boards D or E, the equipment they power, or the 
automatic power transfer feature provided for these boards are not 
precursors to any accident previous evaluated in the Updated Final 
Safety Analysis Report (UFSAR). Therefore, the probability of an 
evaluated accident is not increased by modifying this equipment. The 
proposed deletion of the requirement to maintain the automatic 
transfer capability for the power supply to the LPCI inboard 
injection valves, RHR [residual heat removal] minimum flow valves 
and recirculation pump discharge valves does not change the number 
of Emergency Core Cooling System (ECCS) subsystems credited in the 
BFN licensing basis. The proposed change does not affect the 
operational characteristics or function of systems, structures, or 
components (SSCs), the interfaces between credited SSCs and other 
plant systems, or the reliability of SSCs. The proposed change does 
not impact the capability of credited SSCs to perform their required 
safety functions.
    Therefore, the proposed TS changes will not significantly 
increase the consequences of an accident previously evaluated.
    2. Does the proposed Technical Specification change create the 
possibility of a new or different kind of accident from any accident 
previously evaluated?
    Response: No.
    The proposed deletion of the requirement to maintain an 
automatic transfer capability for the power supply to the LPCI 
inboard injection valves, RHR minimum flow valves and recirculation 
pump discharge valves does not introduce new equipment, which could 
create a new or different kind of accident.
    The proposed change does not alter the manner in which equipment 
operation is initiated, nor will the functional demands on credited 
equipment be changed. The capability of credited SSCs to perform 
their required function will not be affected by the proposed change. 
In addition, the proposed change does not affect the interaction of 
plant SSCs with other plant SSCs whose failure or malfunction can 
initiate an accident or transient. As such, no new failure modes are 
being introduced. No new external threats, release pathways, or 
equipment failure modes are created. Therefore, the proposed 
deletion of the requirement to maintain an automatic transfer 
capability for the power supply to the LPCI inboard injection 
valves, RHR minimum flow valves and recirculation pump discharge 
valves will not create a possibility for an accident of a new or 
different type than those previously evaluated.
    3. Does the proposed Technical Specification change involve a 
significant reduction in a margin of safety?
    Response: No.
    The proposed deletion of the requirement to maintain an 
automatic transfer capability for the power supply to the LPCI 
inboard injection valves, RHR minimum flow valves and recirculation 
pump discharge valves does not change the conditions, operating 
configurations, or minimum amount of operating equipment credited in 
the safety analyses for accident or transient mitigation. The 
proposed change does not alter the assumptions contained in the 
safety analyses. The proposed change does not alter the manner in 
which safety limits, limiting safety system settings or limiting 
conditions for operation are determined. The proposed change does 
not impact the safety analysis credited redundancy or availability 
of SSCs required for accident or transient mitigation, or the 
ability of the plant to cope with design basis events as assumed in 
safety analyses. In addition, no changes are proposed in the manner 
in which the credited SSCs provide plant protection or which create 
new modes of plant operation. The requirements of 10 CFR 50.46 and 
Appendix K continue to be met. 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, 6A West Tower, Knoxville, Tennessee 37902.
    NRC Branch Chief: Douglas A. Broaddus.

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

[[Page 24931]]

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. Publicly available records will be accessible from the 
Agencywide Documents Access and Management System (ADAMS) Public NRC 
Library 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 email to 
[email protected].

Carolina Power and Light Company, Docket Nos. 50-325 and 50-324, 
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North 
Carolina

    Date of application for amendments: April 29, 2010, as supplemented 
by letters dated June 9, July 22, July 29, September 29, October 12, 
November 9, November 18, and December 16, 2010; March 16, and April 6, 
2011.
    Brief description of amendments: The proposed license amendments 
revised the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, 
Technical Specification 5.6.5.b by adding AREVA topical report, BAW-
10247PA, ``Realistic Thermal-Mechanical Fuel Rod Methodology for 
Boiling Water Reactors,'' Revision 0, April 2008, to the list of 
analytical methods that have been reviewed and approved by the NRC for 
determining core operating limits. The proposed amendments changed the 
BSEP Technical Specifications to support transition to ATRIUM 10XM fuel 
and associated core design methodologies.
    Date of issuance: April 8, 2011.
    Effective date: Date of issuance, to be implemented prior to 
startup from the 2011 refueling outage (RFO) for Unit 2, and prior to 
startup from the 2012 RFO for Unit 1.
    Amendment Nos.: Unit 1--256 and Unit 2--284.
    Renewed Facility Operating License Nos. DPR-71 and DPR-62: 
Amendments revised the Technical Specifications.
    Date of initial notice in Federal Register: August 10, 2010 (75 FR 
48373). The supplemental letters dated June 9, July 29, September 29, 
October 12, November 9, November 18, and December 16, 2010; March 16 
and April 6, 2011, 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 April 8, 2011.
    No significant hazards consideration comments received: No.

Carolina Power and Light Company, Docket Nos. 50-325 and 50-324, 
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North 
Carolina

    Date of application for amendments: April 29, 2010, as supplemented 
by letters dated June 9, July 22, July 29, September 29, October 12, 
November 9, November 18, and December 16, 2010, and April 6, 2011.
    Brief description of amendments: The proposed license amendments 
revised the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, 
Technical Specification (TS) 5.6.5.b by adding the AREVA, topical 
report, ANP-10298PA, ``ACE/ATRIUM 10XM Critical Power Correlation,'' 
Revision 0, March 2010, to the list of analytical methods that have 
been reviewed and approved by the NRC for determining core operating 
limits. The proposed amendments changed the BSEP Units 1 and 2 TSs to 
support transition to ATRIUM 10XM fuel and associated core design 
methodologies.
    Date of issuance: April 8, 2011.
    Effective date: Upon date of issuance and implemented prior to 
startup from the 2011 refueling outage (RFO) for Unit 2 and prior to 
start-up from the 2012 RFO for Unit 1.
    Amendment Nos.: Unit 1--257 and Unit 2--285.
    Renewed Facility Operating License Nos. DPR-71 and DPR-62: 
Amendments revised the TSs.
    Date of initial notice in Federal Register: August 10, 2010 (75 FR 
48372). The supplemental letters dated June 9, July 29, September 29, 
October 12, November 9, November 18, and December 16, 2010, and April 
6, 2011, 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 April 8, 2011.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit 
2, Pope County, Arkansas

    Date of application for amendment: June 17, 2010, as supplemented 
by letters dated January 17, 20, and 31 and March 7, 2011.
    Brief description of amendment: The amendment revised Technical 
Specification 6.5.16, ``Containment Leakage Rate Testing Program,'' to 
allow for the extension of the 10-year frequency of the Arkansas 
Nuclear One, Unit 2 Type A or Integrated Leak Rate Test to 15 years on 
a permanent basis.
    Date of issuance: April 7, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment No.: 292.
    Renewed Facility Operating License No. NPF-6: Amendment revised the 
Technical Specifications/license.
    Date of initial notice in Federal Register: July 27, 2010 (75 FR 
44024). The supplemental letters dated January 17, 20, and 31 and March 
7, 2011, 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 amendment is contained 
in a Safety Evaluation dated April 7, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, 
Braidwood Station, Units 1 and 2, Will County, Illinois; Docket Nos. 
STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle 
County, Illinois

    Date of application for amendment: December 14, 2010.
    Brief description of amendment: The amendments revised Technical 
Specification (TS) 5.5.9, ``Steam Generator (SG) Program,'' to exclude 
portions of the tubes within the tubesheet from periodic steam 
generator (SG) inspections and plugging or repair. In addition, these 
amendments revise TS 5.6.9, ``Steam Generator (SG) Tube

[[Page 24932]]

Inspection Report,'' to remove reference to previous interim alternate 
repair criteria and provide reporting requirements specific to the 
temporary alternate criteria.
    Date of issuance: April 13, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days for Braidwood Station, Units 1 and 2, for Byron Station, 
Unit Nos. 1 and 2 prior to conducting the SG inspections required by TS 
5.5.9 for the Byron Station, Unit No. 2, fall 2011 refueling outage 
(B2R16).
    Amendment Nos.: 166 and 172.
    Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and NPF-66: 
The amendments revised the Technical Specifications and License.
    Date of initial notice in Federal Register: February 1, 2011 (76 FR 
5617).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated April 13, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle 
County Station, Units 1 and 2, LaSalle County, Illinois

    Date of application for amendments: April 19, 2010, as supplemented 
by letters dated October 15, 2010, and March 14, 2011.
    Brief description of amendments: The amendment request proposed 
changes to the technical specifications (TSs) to revise TS 3.4.11, 
``RCS [reactor coolant system] Pressure and Temperature (P/T) [or P-T] 
Limits,'' to incorporate revised P-T curves that are valid for up to 32 
effective full power years (EFPYs) of operation.
    Date of issuance: April 15, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: 201/188.
    Facility Operating License Nos. NPF-11 and NPF-18: The amendments 
revised the Technical Specifications and License.
    Date of initial notice in Federal Register: June 29, 2010 (75 FR 
37475).
    The October 15, 2010, and March 14, 2011, supplements contained 
clarifying information and did not change the NRC staff's initial 
proposed finding of no significant hazards consideration.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated April 15, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick 
Generating Station (LGS), Units 1 and 2, Montgomery County, 
Pennsylvania

    Date of application for amendment: March 25, 2010, as supplemented 
by letters dated April 26, 2010, June 29, 2010, July 22, 2010, July 28, 
2010 (2), August 10, 2010, August 12, 2010 (2), August 30, 2010, 
December 17, 2010, and January 7, 2011.
    Brief description of amendment: The changes implemented an increase 
of approximately 1.65 percent in rated thermal power from the current 
licensed thermal power of 3458 megawatts thermal (MWt) to 3515 MWt. The 
changes are based on increased feedwater flow measurement accuracy, 
which will be achieved by utilizing Cameron International (formerly 
Caldon) CheckPIus Leading Edge Flow Meter ultrasonic flow measurement 
instrumentation. The changes also modified certain technical 
specification setpoints and channel surveillance requirements 
associated with average power range monitor simulated thermal power. 
Additionally, the proposed changes include a modification to the 
Standby Liquid Control System, that allows operators to select two 
pumps instead of three for the automatic start function on an 
Anticipated Transient Without Scram signal.
    Date of issuance: April 8, 2011.
    Effective date: For LGS Unit 1, as of the date of issuance and 
shall be implemented within 90 days of issuance. For LGS Unit 2, as of 
the date of issuance and shall be implemented within 90 days of the 
completion of refueling outage Li2R11.
    Amendment Nos.: 201 and 163.
    Facility Operating License Nos. NPF-39 and NPF-85. These amendments 
revised the license and the technical specifications.
    Date of initial notice in Federal Register: June 8, 2010 (75 FR 
32512). The supplements dated April 26, 2010, June 29, 2010, July 22, 
2010, July 28, 2010 (2), August 10, 2010, August 12, 2010 (2), August 
30, 2010, December 17, 2010, and January 7, 2011, 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 determination.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated April 8, 2011.
    No significant hazards consideration comments received: No.

FirstEnergy Nuclear Operating Company, et al., Docket No. 50-440, Perry 
Nuclear Power Plant, Unit 1, Lake County, Ohio

    Date of application for amendment: October 21, 2010, as 
supplemented by letters dated February 2, 2011, and March 17, 2011.
    Brief description of amendment: This license amendment modified 
Technical Specification 2.1.1, ``Reactor Core SLs,'' by incorporating 
revised safety limit minimum critical power ratio values resulting from 
a plant-specific analysis performed for PNPP Cycle 14 core.
    Date of issuance: April 18, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 155.
    Facility Operating License No. NPF-58: This amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: January 11, 2011 (76 FR 
1649).
    The February 2, 2011 and March 17, 2011 supplements contained 
clarifying information and did not change the NRC staff's initial 
proposed finding of significant hazards consideration published in the 
Federal Register (76 FR 1649, January 11, 2011).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated April 18, 2011.
    No significant hazards consideration comments received: No.

NextEra Energy, Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point 
Beach Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowoc 
County, Wisconsin

    Date of application for amendments: December 8, 2008, as 
supplemented by letters dated January 16, January 27, February 20, 
April 17 (two letters), May 8, May 15, June 1, July 24, August 20, 
September 4 (two letters), September 10, October 2, November 20, 
November 25, and December 17 of 2009; January 14, February 4 (two 
letters), March 5, April 20, July 8, July 29, August 12, September 3, 
October 12, and November 16 of 2010; January 27 and February 10 of 
2011.
    Brief description of amendments: The amendments modified the 
requirements of TS 3.4.16, ``RCS [reactor coolant system] Specific 
Activity,'' and TS 3.7.13, ``Secondary Specific Activity,'' as related 
to the use of an alternate source term (AST) associated with accident 
offsite and control room dose consequences. Implementation of the AST 
supports adoption of the control room envelope habitability controls in 
accordance with NRC-approved TS Task

[[Page 24933]]

Force (TSTF) Standard Technical Specification change traveler TSTF-448, 
Revision 3, ``Control Room Habitability.'' To support this change, the 
amendment modified the following: 1) TS 1.1, ``Definitions''; 2) TS 
3.7.9, ``Control Room Emergency Filtration System (CREFS),'' Limiting 
Condition for Operation 3.7.9, including Surveillance Requirements 
3.7.9.2, 3.7.9.3, and 3.7.9.6; 3) TS 5.5.15, ``Containment Leakage Rate 
Testing Program''; 4) the addition of TS 5.5.18, ``Control Room 
Envelope Habitability.'' Finally, TS 5.6.4, ``Core Operating Limits 
Report (COLR),'' will incorporate the addition of the NRC-approved 
analytical methodology as described in WCAP-16259-P-A, ``Westinghouse 
Methodology for Application of 3-D Transient Neutronics to Non-LOCA 
Analyses.''
    Date of issuance: April 14, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days.
    Amendment Nos.: 240, 244.
    Renewed Facility Operating License Nos. DPR-24 and DPR-27: 
Amendments revised the License, Appendix C, and the Technical 
Specifications.
    Date of initial notice in Federal Register: October 12, 2010 (75 FR 
62602).
    The supplemental letters contained clarifying information and did 
not change the staff's initial proposed finding of no significant 
hazards consideration.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated April 14, 2011.
    No significant hazards consideration comments received: No.

Virginia Electric and Power Company, Docket No. 52-008, North Anna 
Early Site Permit (ESP) Site, Louisa County, Virginia

    Date of amendment request: September 2, 2010.
    Description of amendment request: The amendment revised the North 
Anna Early Site Permit by deleting condition 3.G, which prescribes the 
notification and certification requirements associated with beginning 
the site preparation and preliminary construction activities approved 
by ESP-003.
    Date of issuance: April 13, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment No.: Two.
    Early Site Permit No. ESP-003: Amendment revised the North Anna 
site ESP.
    Public comments requested as to proposed no significant hazards 
consideration (NSHC): Yes.
    Date of initial notice in the Federal Register (FR): November 30, 
2010 (75 FR 74105). The November 30, 2010 FR notice provided an 
opportunity to submit comments on the Commission's proposed NSHC 
determination. No comments have been received.
    The Commission's related evaluation of the requested approval of 
the amendment, and state consultation, are contained in a safety 
evaluation dated April 13, 2011. The NRC staff determined that the 
amendment satisfied the categorical exclusion criterion of 10 CFR 
51.22(c) and no environmental assessment was required.
    Attorney for the licensee: Lillian M. Cuoco, Senior Counsel, 
Dominion Resources Services, Inc., 120 Tredegar Street, RS-2, Richmond, 
VA 23219.
    NRC Branch Chief: Hossein Hamzehee.

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: May 6, 2010.
    Brief description of amendment: These amendments revised TS 4.2.1, 
``Fuel Assemblies,'' to add Optimized ZIRLOTM as an 
acceptable fuel rod cladding material. In addition, the amendments 
revised TS 5.6.5.b to add the Westinghouse topical report for Optimized 
ZIRLOTM to the list of analytical methods used to determine 
the core operating limits.
    Date of issuance: April 14, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 263 and 244.
    Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments 
changed the licenses and the technical specifications.
    Date of initial notice in Federal Register: August 27, 2010 (75 FR 
52781).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated April 14, 2011.
    No significant hazards consideration comments received: No.

Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Coffey County, Kansas

    Date of amendment request: October 21, 2010.
    Brief description of amendment: The amendment corrected a 
typographical error in Technical Specification (TS) 5.0, 
``ADMINISTRATIVE CONTROLS.'' The current TSs, on page 5.0-31, has two 
paragraphs numbered as 5.7.2.d.3. The amendment renumbered the second 
paragraph as 5.7.2.d.4.
    Date of issuance: April 19, 2011.
    Effective date: As the date of issuance and shall be implemented 
within 90 days of the date of issuance.
    Amendment No.: 196.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Operating License and Technical Specifications.
    Date of initial notice in Federal Register: December 14, 2010 (75 
FR 77917).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated April 19, 2011.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 21st day of April 2011.

    For the Nuclear Regulatory Commission.
Robert A. Nelson,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2011-10405 Filed 5-2-11; 8:45 am]
BILLING CODE 7590-01-P