Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, 34337-34347 [E8-13218]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 73, Number 117 (Tuesday, June 17, 2008)]
[Notices]
[Pages 34337-34347]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-13218]


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NUCLEAR REGULATORY COMMISSION


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 staff) 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 May 22, 2008 to June 4, 2008. The last 
biweekly notice was published on June 3, 2008 (73 FR 31717).

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 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, Rulemaking, 
Directives and Editing Branch, 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 delivered to Room 6D44, Two White Flint North, 11545 Rockville Pike, 
Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. 
Copies of written comments received may be examined at the Commission's 
Public Document Room (PDR), located at One White Flint North, Public 
File Area O1F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland. The filing of requests for a hearing and petitions for leave 
to intervene is discussed below.
    Within 60 days after the date of publication of this notice, 
person(s) may file a request for a hearing with respect to issuance of 
the amendment to the subject facility operating license and any person 
whose interest may be affected by this proceeding and who wishes to 
participate as a party in the proceeding must file a written request 
via electronic submission through the NRC E-Filing system for a hearing 
and a petition for leave to intervene. Requests for a hearing and a 
petition for leave to intervene shall be filed in accordance with the 
Commission's ``Rules of Practice for Domestic Licensing Proceedings'' 
in 10 CFR part 2. Interested person(s) should consult a current copy of 
10 CFR 2.309, which is available at the Commission's PDR, located at 
One White Flint North, Public File Area 01F21, 11555 Rockville Pike 
(first floor), Rockville, Maryland. Publicly available records will be 
accessible from the Agencywide Documents Access and Management

[[Page 34338]]

System's (ADAMS) Public Electronic Reading Room on the Internet at the 
NRC Web site, https://www.nrc.gov/reading-rm/doc-collections/cfr/. If a 
request for a hearing or petition for leave to intervene is filed 
within 60 days, 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 set forth the specific contentions which the petitioner/requestor 
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 
petitioner/requestor shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the petitioner/
requestor intends to rely in proving the contention at the hearing. The 
petitioner/requestor must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
petitioner/requestor 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 petitioner/requestor to relief. A petitioner/
requestor 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, and the Commission has not made a final 
determination on the issue of no significant hazards consideration, the 
Commission will make a final determination on the issue of no 
significant hazards consideration. The final determination will serve 
to decide when the hearing is held. If the final determination is that 
the amendment request involves no significant hazards consideration, 
the Commission may issue the amendment and make it immediately 
effective, notwithstanding the request for a hearing. Any hearing held 
would take place after issuance of the amendment. If the final 
determination is that the amendment request involves a significant 
hazards consideration, any hearing held would take place before the 
issuance of any amendment.
    A request for hearing or a petition for leave to intervene must be 
filed in accordance with the NRC E-Filing rule, which the NRC 
promulgated in August 28, 2007 (72 FR 49139). The E-Filing process 
requires participants to submit and serve 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 a waiver in accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 
five (5) days prior to the filing deadline, the petitioner/requestor 
must contact the Office of the Secretary by e-mail at 
hearingdocket@nrc.gov, or by calling (301) 415-1677, to request (1) a 
digital ID certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and/or (2) 
creation of an electronic docket for the proceeding (even in instances 
in which the petitioner/requestor (or its counsel or representative) 
already holds an NRC-issued digital ID certificate). Each petitioner/
requestor will need to download the Workplace Forms Viewer(tm) to 
access the Electronic Information Exchange (EIE), a component of the E-
Filing system. The Workplace Forms Viewer\TM\ is free and is available 
at https://www.nrc.gov/site-help/e-submittals/install-viewer.html. 
Information about applying for a digital ID certificate is available on 
NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/
apply-certificates.html.
    Once a petitioner/requestor has obtained a digital ID certificate, 
had a docket created, and downloaded the EIE viewer, it 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 https://www.nrc.gov/
site-help/e-submittals.html. A filing is considered complete at the 
time the filer submits its documents through EIE. To be timely, an 
electronic filing must be submitted to the EIE 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 
EIE 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 may seek assistance through the 
``Contact Us'' link located on the NRC Web site at https://www.nrc.gov/
site-help/e-submittals.html or by calling the NRC technical help line, 
which is available between 8:30 a.m. and 4:15 p.m., Eastern Time, 
Monday through Friday. The help line number is (800) 397-4209 or 
locally, (301) 415-4737.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file a motion, 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:

[[Page 34339]]

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.
    Non-timely requests and/or petitions and contentions will not be 
entertained absent a determination by the Commission, the presiding 
officer, or the Atomic Safety and Licensing Board that the petition 
and/or request should be granted and/or the contentions should be 
admitted, based on a balancing of the factors specified in 10 CFR 
2.309(c)(1)(i)-(viii). To be timely, filings must be submitted no later 
than 11:59 p.m. Eastern Time on the due date.
    Documents submitted in adjudicatory proceedings will appear in 
NRC's electronic hearing docket which is available to the public at 
https://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant 
to an order of the Commission, an Atomic Safety and Licensing Board, or 
a 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. 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.
    For further details with respect to this amendment action, see the 
application for amendment which is available for public inspection at 
the Commission's PDR, located at One White Flint North, Public File 
Area 01F21, 11555 Rockville Pike (first floor), Rockville, Maryland. 
Publicly available records will be accessible from the ADAMS Public 
Electronic Reading Room on the Internet at the NRC Web site, https://
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 pdr@nrc.gov.
    AmerGen Energy Company, LLC, et al., Docket No. 50-219, Oyster 
Creek Nuclear Generating Station (Oyster Creek), Ocean County, New 
Jersey.
    Date of amendment request: October 18, 2007.
    Description of amendment request: The proposed amendment would 
modify Technical Specification (TS) 4.5.M.1.e.1, ``Containment 
System,'' concerning the mechanical snubbers functional test acceptance 
criteria. Specifically, the change would replace the snubber breakaway 
test with a drag force test.
    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 change modifies Technical Specifications (TS) 
Section 4.5.M.1.e.1 concerning the Mechanical Snubbers Functional 
Test Acceptance Criteria, specifically, replacement of the snubber 
breakaway test with the drag force test. [Title 10 of the Code of 
Federal Regulations (10 CFR), Part] 50.55a(b)(3)(v) permits the use 
of [American Society of Mechanical Engineers (ASME) Operations and 
Maintenance (OM) Code], Subsection ISTD, in lieu of the ASME Code, 
Section XI, for the inservice testing of snubbers. Subsection ISTD 
of the ASME OM-Code, ``Preservice and Inservice Examination and 
Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor 
Nuclear Power Plants,'' provides the requirements for snubber 
testing. A requirement to perform the breakaway test no longer 
exists in the ASME OM Code. Current ASME OM Code requirements 
require a drag force test. The drag force test is a more 
encompassing representation of overall snubber resistance to thermal 
movement because it is performed over the entire working range of 
the snubber stroke. Therefore, a drag force test should be used 
rather than the breakaway or ``force that initiated free movement'' 
as currently worded in the [Oyster Creek Generating Station] TS. In 
addition to the above, the breakaway test is intended to be 
performed prior to any movement of the snubber. This is an 
impractical test situation, because the snubber has typically moved 
while the unit is cooling down, and the piping experiences thermal 
cycles.
    The percentage of snubbers sampled and the period between 
inspections has not changed. Also, the way the snubber functions has 
not changed, only the method of testing that ensures continued 
functionality of it. Elimination of the breakaway test will not 
reduce the ability of snubbers to perform their intended design 
function. Drag force testing as defined in the TS will ensure 
adequate demonstration of snubber performance. Also, this change 
will not increase the probability of malfunction of plant equipment, 
or the failure of plant structures, systems, or components. Piping 
systems that include snubbers in their configuration will still be 
capable of performing their safety function.
    Therefore, the proposed change[s 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 accident previously 
evaluated?
    Response: No.
    The proposed change does not affect the assumed accident 
performance of the Reactor Coolant Pressure Boundary, nor any plant 
structure, system, or component previously evaluated. The proposed 
change does not involve the installation of new equipment, and 
installed equipment is not being operated in a new or different 
manner. The change deletes the breakaway test for snubbers, which is 
no longer required by the ASME OM Code, and replaces it with a drag 
force test to ensure snubber functionality consistent with the ASME 
OM Code. No set points are being changed which would alter the 
dynamic response of plant equipment, and the design function of 
systems associated with snubbers will not be altered. Accordingly, 
no new failure modes or accident initiators are introduced.
    Therefore, the proposed change[s 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 proposed change does not affect the function of any safety 
systems or response during plant transients. There are no changes 
proposed which alter the set points at which protective actions are 
initiated, and there is no change to the operability requirements 
for equipment assumed to operate for accident mitigation. The 
snubbers will continue to perform their design function. This change 
deletes the breakaway test for snubbers, which is no longer required 
by the ASME OM Code, and replaces it with a drag force test. 
Therefore, the proposed changes do not involve a significant 
reduction in any margin of safety.
    The NRC staff has reviewed the licensee's analysis and, based on 
this review, and with the changes noted above, 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: Thomas S. O'Neill, Associate General 
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, 
Warrenville, IL 60555.
    NRC Branch Chief: Harold K. Chernoff.
    AmerGen Energy Company, LLC, et al., Docket No. 50-219, Oyster 
Creek Nuclear Generating Station (Oyster Creek), Ocean County, New 
Jersey.
    Date of amendment request: March 10, 2008.
    Description of amendment request: The proposed amendment would 
relocate the pressure and temperature limit curves from the Technical 
Specifications (TSs) to the licensee controlled ``Pressure and 
Temperature

[[Page 34340]]

Limits Report.'' Additionally, the proposed change would update other 
TS references from the TS contained curves to those in the Pressure and 
Temperature Limits Report.
    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 change modifies the Technical Specifications (TS) 
Section 1.0 (``Definitions''), Limiting Conditions for Operation 
Section 3.3 (``Reactor Coolant''), Surveillance Requirement 4.3 
(``Reactor Coolant''), and 6.0 (``Administrative Controls''), to 
delete reference to the [Pressure-Temperature (P-T)] curves and 
include reference to the [pressure-temperature limits report 
(PTLR)]. This change adopts the methodology of SIR-05-044-A, 
``Pressure-Temperature Limits Report Methodology for Boiling Water 
Reactors,'' dated April 2007 for preparation of the pressure and 
temperature curves, and incorporates the guidance of TSTF-419-A 
(``Revised PTLR Definition and References in ISTS 5.6.6, RCS 
PTLR''). [As stated in] an NRC [safety evaluation report] dated 
February 6, 2007, ``the NRC staff has found that SIR-05-044 is 
acceptable for referencing in licensing applications for General 
Electric designed boiling water reactors to the extent specified and 
under the limitations delineated in the [topical report (TR)] and in 
the enclosed final [safety evaluation].'' As part of this change, 
the PTLR based on the methodology and template provided in SIR-05-
044 is being supplied for review. The P-T curves utilize the 
methodology of SIR-05-044-A.
    The NRC has established requirements in Appendix G to [Title 10 
of the Code of Federal Regulations (10 CFR) Part 50] to protect the 
integrity of [the reactor coolant pressure boundary (RCPB)] in 
nuclear power plants. Additionally, 10 CFR Part 50, Appendix H, 
provides the NRC staff's criteria for the design and implementation 
of RPV material surveillance programs for operating lightwater 
reactors. Implementing this NRC-approved methodology does not reduce 
the ability to protect the RCPB as specified in Appendix G, nor will 
this change increase the probability of malfunction of plant 
equipment, or the failure of plant structures, systems, or 
components. Incorporation of the new methodology for calculating P-T 
curves from the TS to the PTLR provides an equivalent level of 
assurance that the RCPB is capable of performing its intended safety 
functions. Thus, the proposed change does not affect the probability 
or consequences of an accident previously evaluated.
    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 accident previously 
evaluated?
    Response: No.
    The proposed change does not affect the assumed accident 
performance of the RCPB, nor any plant structure, system, or 
component previously evaluated. The proposed change does not involve 
the installation of new equipment, and installed equipment is not 
being operated in a new or different manner. The change in 
methodology ensures that the RCPB remains capable of performing its 
safety functions. No setpoints are being changed which would alter 
the dynamic response of plant equipment. Accordingly, no new failure 
modes are introduced which could introduce the possibility of a new 
or different kind of accident from any previously evaluated.
    This change adopts the methodology of SIR-05-044-A, ``Pressure-
Temperature Limits Report Methodology for Boiling Water Reactors,'' 
dated April 2007 for preparation of the pressure and temperature 
curves, and incorporates the guidance of TSTF-419-A (``Revise PTLR 
Definition and References in ISTS 5.6.6, RCS PTLR''). In an NRC SER 
dated February 6, 2007, the NRC staff has found that SIR-05-044 is 
acceptable for referencing in licensing applications for General 
Electric designed boiling water reactors.
    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 proposed change does not affect the function of the RCPB or 
its response during plant transients. There are no changes proposed 
which alter the setpoints at which protective actions are initiated, 
and there is no change to the operability requirements for equipment 
assumed to operate for accident mitigation. This change adopts the 
methodology of SIR-05-044-A, ``Pressure-Temperature Limits Report 
Methodology for Boiling Water Reactors,'' dated April 2007 for 
preparation of the P-T curves. 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, and with the changes noted above, 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: Thomas S. O'Neill, Associate General 
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, 
Warrenville, IL 60555.
    NRC Branch Chief: Harold K. Chernoff.
    Dominion Energy Kewaunee, Inc. Docket No. 50-305, Kewaunee Power 
Station, Kewaunee County, Wisconsin.
    Date of amendment request: April 14, 2008.
    Description of amendment request: The proposed amendment would 
modify the Technical Specifications to allow the main steam line 
isolation (SLI) circuitry to be inoperable when both Main Steam 
Isolation Valves (MSIVs) are closed and de-activated.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment would allow the SLI instrumentation to be 
inoperable when both MSIVs are already closed and de-activated. When 
both MSIVs are closed, the SLI function is already accomplished and 
the SLI instrumentation is no longer needed. The proposed amendment 
does not involve a physical alteration of the plant or a functional 
change in the methods used to respond to any evaluated plant 
accident. The isolation function is accomplished either by SLI 
instrumentation or manually closing the MSIVs. No new or different 
equipment is being installed and no installed equipment is being 
removed or modified. The proposed amendment would not alter the 
parameters within which the plant is normally operated or the 
setpoints which initiate protective or mitigative actions.
    With both MSIVs closed, the SLI instrumentation is not required 
to be operable since its safety function has already been 
accomplished. Addition of the proposed new footnote would not 
adversely impact any of the previously evaluated accidents described 
in the KPS [Kewaunee Power Station] USAR [Updated Safety Analysis 
Report].
    Therefore, the proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed amendment does not involve a physical alteration of 
the plant or a functional change in the methods used to respond to 
plant accidents or transients. No new or different equipment is 
being installed and no installed equipment is being removed or 
modified. The proposed amendment would not alter the parameters 
within which the plant is normally operated or the setpoints which 
initiate protective or mitigative actions. The design function of 
the SLI instrumentation would not be changed. With both MSIVs 
closed, the safety function associated with the SLI instrumentation 
has already been accomplished. Allowing the SLI instrumentation to 
be inoperable when both

[[Page 34341]]

MSIVs are closed and de-activated does not functionally impact how 
the plant would respond to any previously evaluated accidents. No 
new failure mechanisms, malfunctions, or accident initiators not 
considered in the design and licensing bases are introduced by the 
proposed amendment.
    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.
    Margin of safety is established through the design of the 
systems, structures, and components, the parameters within which the 
plant is operated, and the establishment of setpoints for the 
actuation of equipment relied upon to respond to an event. The 
proposed TS amendment does not adversely impact any plant structure, 
system or component that is relied upon for accident mitigation. The 
design of the SLI function is not affected by the proposed change. 
Closure and de-activation of the MSIVs represents an increase in 
functional margin as a deactivated valve has no opportunity to be 
inadvertently opened. The proposed amendment also does not adversely 
affect the setpoints or parameters under which the SLI 
instrumentation is operated. Station operations and the SLI function 
would not be adversely affected by the proposed change, because the 
isolation function capability is maintained throughout the 
applicable modes of operation. The proposed change does not alter 
any design basis or safety limit established in the KPS USAR.
    Therefore, the proposed amendment to the KPS TS 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: Lillian M. Cuoco, Senior Counsel, Dominion 
Resources Services, Inc., 120 Tredegar Street, Richmond, VA 23219.
    NRC Branch Chief: Lois James.
    Dominion Nuclear Connecticut Inc., et al., Docket Nos. 50-336 and 
50-423, Millstone Power Station, Unit Nos. 2 and 3, New London County, 
Connecticut.
    Date of amendment request: August 15, 2007.
    Description of amendment request: The proposed amendment would 
modify Technical Specification (TS) 3.3.3.1, ``Radiation Monitoring,'' 
TS 3.4.6.1, ``Reactor Coolant System Leakage Detection Systems,'' and 
Surveillance Requirements 4.4.6.1, ``Reactor Coolant System Leakage 
Detection Systems.'' Specifically, the proposed amendment would remove 
credit for the gaseous radiation monitor for Reactor Coolant System 
leakage detection. Improvements in nuclear fuel reliability over time 
have resulted in the reduction of effectiveness of the monitors in 
detecting very small leaks and very small changes in the leakrate. The 
proposed change also addresses the condition when the remaining 
monitoring systems are all inoperable.
    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 has been evaluated and determined to not 
increase the probability or consequences of an accident previously 
evaluated. The proposed change does not make any hardware changes 
and does not alter the configuration of any plant system, structure 
or component (SSC). The containment atmosphere gaseous radioactivity 
monitor is not credited for use in the initiation of any protective 
functions. The proposed change only removes the containment 
atmosphere gaseous radioactivity monitor for meeting the operability 
requirement for TS 3.4.6.1. Therefore, the probability of occurrence 
of an accident is not increased. The TS will continue to require 
diverse means of leakage detection equipment, thus ensuring that 
leakage due to cracks would continue to be identified prior to 
breakage and the plant shutdown accordingly. Additionally, the 
function of this equipment is not modeled in the MPS2 or MPS3 
probabilistic risk assessment and therefore its removal from the 
Technical Specifications has no impact on core damage frequency or 
large early release frequency. Therefore, the consequences of an 
accident are not increased.
    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 the use or installation of 
new equipment and the currently installed equipment will not be 
operated in a new or different manner. No new or different system 
interactions are created and no new processes are introduced. The 
proposed changes will not introduce any new failure mechanisms, 
malfunctions, or accident initiators not already considered in the 
design and licensing bases. The proposed change does not affect any 
SSC associated with an accident initiator. Based on this evaluation, 
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 does not make any alteration to any RCS 
[Reactor Coolant System] leakage detection components. The proposed 
change only removes the gaseous channel of the containment 
atmosphere radioactivity monitor for meeting the operability 
requirement for TS 3.4.6.1. The proposed amendment continues to 
require diverse means of leakage detection equipment with capability 
to promptly detect RCS leakage. Although not required by TS, 
additional diverse means of leakage detection capability are 
available. Based on this evaluation, the proposed change does not 
involve a significant reduction in a margin of safety.
    Based on the above, DNC [Dominion Nuclear Connecticut] concludes 
that the proposed amendment involves no significant hazards 
consideration under the standards set forth in 10 CFR 50.92, and a 
finding of ``no significant hazards consideration'' is justified.

    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: Lillian M. Cuoco, Senior Nuclear Counsel, 
Dominion Nuclear Connecticut, Inc., Waterford, CT 06141-5127.
    NRC Branch Chief: Harold K. Chernoff.
    Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-
455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois.
    Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units. 1 
and 2, Will County, Illinois.
    Date of amendment request: March 18, 2008.
    Description of amendment request: The proposed amendments would 
revise the technical specification (TS) surveillance requirement (SR) 
numbering for two engineered safety feature actuation system (ESFAS) 
instrumentation SRs that were revised in previous license amendments 
issued by the Nuclear Regulatory Commission (NRC) staff. The revised 
numbering scheme in the previous amendments introduced inconsistencies 
within TS 3.3.2. In addition, the proposed amendments request an 
extension of the 120-day period for implementation of the changes to 
SRs 3.3.2.6 and 3.3.2.7, approved in the previous license amendments, 
to 30 days following approval of the proposed amendments.
    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

[[Page 34342]]

consideration, which is presented below:

    1. The proposed changes do not involve a significant increase in 
the probability or consequences of an accident previously evaluated.
    The proposed revision to the numbering of two ESFAS 
instrumentation SRs and extension of a previously approved license 
amendment implementation period are purely administrative in nature, 
and as such, do not increase the probability of any accident 
previously evaluated. The proposed changes do not affect accident 
initiators or precursors nor alter the design assumptions, 
conditions, or configuration of the facility or the manner in which 
the plant is operated and maintained. The proposed changes will not 
modify any system interface, nor will they affect the probability of 
any event initiators. Therefore, the proposed changes do not 
increase the probability of an accident previously evaluated.
    Since the proposed changes are purely administrative, the 
changes will not alter or prevent structures, systems, and 
components from performing their intended function to mitigate the 
consequences of an initiating event, within the assumed acceptance 
limits. The proposed amendment does not change the response of the 
plant to any accidents and has no impact on the reliability of the 
ESFAS signals. The ESFAS will remain highly reliable, and the 
proposed changes will not result in an increase in the risk of plant 
operation. There will be no degradation in the performance of, or an 
increase in the number of challenges imposed on safety-related 
equipment assumed to function during an accident situation. The 
proposed changes do not affect the source term, containment 
isolation, or radiological release assumptions used in evaluating 
the radiological consequences of any accident previously evaluated. 
Therefore, there will not be an increase in the consequences of any 
accidents.
    2. The proposed changes do not create the possibility of a new 
or different kind of accident from any accident previously 
evaluated.
    The proposed revision to the numbering of two ESFAS 
instrumentation SRs and extension of a previously approved license 
amendment implementation period are purely administrative in nature. 
There are no hardware changes nor are there any changes in the 
method by which any safety-related plant system performs its safety 
function. The proposed changes will not affect the normal method of 
plant operation. No performance requirements will be affected or 
eliminated. The proposed changes will not result in physical 
alteration to any plant system nor will there be any change in the 
method by which any safety-related plant system performs its safety 
function. There will be no setpoint changes or changes to accident 
analysis assumptions.
    No new accident scenarios, transient precursors, failure 
mechanisms, or limiting single failures are introduced as a result 
of these changes. There will be no adverse effect or challenges 
imposed on any safety-related system as a result of these changes. 
Therefore, the proposed changes do not create the possibility of a 
new or different kind of accident from any [accident] previously 
evaluated.
    3. The proposed changes do not involve a significant reduction 
in a margin of safety.
    The proposed revision to the numbering of two ESFAS 
instrumentation SRs and extension of a previously approved license 
amendment implementation period are purely administrative in nature. 
Therefore, the proposed changes do not affect the acceptance 
criteria for any analyzed event, nor is there a change to any safety 
analysis limit. There will be no effect on the manner in which 
safety limits, limiting safety system settings, or limiting 
conditions for operation are determined nor will there be any effect 
on those plant systems necessary to assure the accomplishment of 
protection functions. There will be no impact on the departure from 
nucleate boiling limits, fuel centerline temperature, or any other 
margin of safety.
    Redundant ESFAS trains are maintained, and diversity with regard 
of the signals that provide engineered safety features actuation is 
also maintained. All signals credited as primary or secondary, and 
all operator actions credited in the accident analyses will remain 
the same. The proposed changes will not result in plant operation in 
a configuration outside the design basis. 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: Mr. Bradley J. Fewell, Associate General 
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, 
Warrenville, IL 60555.
    NRC Branch Chief: Russell Gibbs.
    FPL Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold 
Energy Center, Linn County, Iowa.
    Date of amendment request: December 20, 2007.
    Description of amendment request: The proposed amendment would add 
a Surveillance Requirement to Technical Specification (TS) Section 
3.7.2, ``RWS [River Water Supply] System and UHS [Ultimate Heat 
Sink],'' to require surveillances of the Cedar River depth to assure 
UHS operability.
    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.
    Technical Specifications currently require surveillance of river 
level elevation and temperature. These surveillance requirements are 
unchanged. Adding an additional surveillance requirement to measure 
river depth will not adversely impact the probability or 
consequences of an accident previously evaluated.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    Adding TS Surveillance Requirements to measure river depth does 
not create the possibility of a new or different kind of accident 
from any accident previously evaluated and does not represent a 
change in the methods governing normal plant operation. In addition, 
the proposed change does not alter or eliminate any existing 
requirements. The proposed change does not alter assumptions made in 
the safety analysis. The proposed change is consistent with the 
safety analysis assumptions and current plant operating practice.
    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.
    Per the DAEC [Duane Arnold Energy Center] UFSAR [Updated Final 
Safety Analysis Report], adequate river flow into the lntake 
Structure must be available to meet emergency cooling requirements 
and assure UHS OPERABILITY. Adequate river flow can be assured by 
requiring a minimum river depth of 6.5 inches or greater at the 
lntake Structure. The proposed Surveillance Requirements ensure 
margin to the minimum flow by specifying a depth of 12 inches or 
greater at the lntake Structure. Adding additional surveillance 
requirements for river depth will not adversely impact any 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: Marjan Mashhadi, Florida Power & Light 
Company, 801 Pennsylvania Avenue, Suite 220, Washington, DC 20004.
    NRC Branch Chief: Lois M. James.
    Omaha Public Power District, Docket No. 50-285, Fort Calhoun 
Station, Unit No. 1, Washington County, Nebraska.
    Date of amendment request: April 22, 2008.
    Description of amendment request: The amendment would revise the 
Technical Specifications (TS) 2.7,

[[Page 34343]]

``Electrical Systems,'' Limiting Condition for Operation (LCO) 2.7(2)j. 
to clarify that a single period of operability for one emergency diesel 
generator (DG) is limited to 7 consecutive days and specify that the 
cumulative total time of inoperability for both DGs during any calendar 
month cannot exceed 7 days.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes clarify the AOT [allowed outage time] of TS 
2.7(2)j for DG inoperability but are not less restrictive. Allowed 
outage times and editorial changes such as these are not an 
initiator of any accident previously evaluated. As a result, the 
probability of an accident previously evaluated is not affected. The 
consequences of an accident during the revised AOT are no different 
than the consequences of the same accident during the existing AOT. 
As a result, the consequences of an accident previously evaluated 
are not affected by these changes. The proposed changes do not alter 
or prevent the ability of structures, systems, and components from 
performing their intended 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 release assumptions used in evaluating 
the radiological consequences of an accident previously evaluated. 
Further, the proposed changes do not increase the types or amounts 
of radioactive effluent that may be released offsite, nor 
significantly increase individual or cumulative occupational/public 
radiation exposures. The proposed changes are consistent with the 
safety analysis assumptions and resultant consequences. Therefore, 
the proposed changes 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 accident from any accident previously evaluated?
    Response: No.
    The proposed changes do not involve a 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 proposed changes do not alter any assumptions made in 
the safety analysis. Therefore, the proposed changes do not create 
the possibility of a new or different accident from any accident 
previously evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed changes clarifying the AOT of TS 2.7(2)j for DG 
inoperability do not alter the manner in which safety limits, 
limiting safety system settings or limiting conditions for operation 
are determined. The safety analysis acceptance criteria are not 
affected by these changes. The proposed changes will not result in 
plant operation in a configuration outside of the design basis. 
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: James R. Curtiss, Esq., Winston & Strawn, 
1700 K Street, NW., Washington, DC 20006-3817.
    NRC Branch Chief: Thomas G. Hiltz.

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, Public File Area 01F21, 11555 Rockville Pike (first floor), 
Rockville, Maryland. Publicly available records will be accessible from 
the Agencywide Documents Access and Management Systems (ADAMS) Public 
Electronic Reading Room on the internet at the NRC Web site, https://
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 pdr@nrc.gov.
    AmerGen Energy Company, LLC, Docket No. 50-219, Oyster Creek 
Nuclear Generating Station, Ocean County, New Jersey.
    Date of amendment request: May 16, 2007.
    Description of amendment request: The amendment revises the Oyster 
Creek Technical Specifications (TSs) 3.5.A.6, ``Primary Containment.'' 
Specifically, the amendment revises the actions taken and applicability 
of the requirement to inert the primary containment atmosphere to less 
than 4 percent oxygen (O2) concentration. Additionally, the 
amendment introduces definitions for thermal power and rated thermal 
power including changes for their consistent use within the TSs.
    Date of issuance: May 30, 2008.
    Effective date: As of its date of issuance, and shall be 
implemented within 60 days.
    Amendment No.: 266.
    Facility Operating License No. NPF-86: The amendment revised the 
License and Technical Specifications
    Date of initial notice in Federal Register: March 11, 2008 (73 FR 
13023). The Commission's related evaluation of the amendment is 
contained in a Safety Evaluation dated May 30, 2008.
    No significant hazards consideration comments received: No.
    Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 
50-529, and STN 50-530, Palo Verde Nuclear Generating Station, Units 
No. 2, Maricopa County, Arizona.
    Date of application for amendments: November 14, 2007.
    Brief description of amendments: The amendments revised the 
Technical Specifications by adding Limiting Condition for Operation 
(LCO) 3.0.8 on the inoperability of snubbers using the Consolidated 
Line Item Improvement Process. The amendments also made conforming 
changes to TS LCO 3.0.1.

[[Page 34344]]

These amendments are consistent with the NRC-approved Industry/
Technical Specification Task Force (TSTF) Traveler No. 372, Revision 4, 
``Addition of LCO 3.0.8, Inoperability of Snubbers.''
    Date of issuance: May 30, 2008.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment Nos.: Unit 1--170, Unit 2--170, and Unit 3--170.
    Facility Operating License No. NPF-41, NPF-51, and NPF-74: The 
amendments revised the Operating Licenses and Technical Specifications.
    Date of initial notice in Federal Register: January 29, 2008 (73 FR 
5217). The Commission's related evaluation of the amendment is 
contained in a Safety Evaluation dated May 30, 2008.
    No significant hazards consideration comments received: No.
    Duke Energy Carolinas, LLC, et al., Docket Nos. 50-413 and 50-414, 
Catawba Nuclear Station, Units 1 and 2, York County, South Carolina.
    Date of application for amendments: February 15, 2008.
    Brief description of amendments: The amendments authorize a change 
to the UFSAR requiring an inspection of each ice condenser within 24 
hours of experiencing a seismic event greater than or equal to an 
operating basis earthquake within the 5-week period after ice basket 
replenishment has been completed to confirm that adverse ice fallout 
has not occurred which could impede the ability of the ice condenser 
lower inlet doors to open. This action would be taken, in lieu of 
requiring a 5-week waiting period following ice basket replenishment, 
prior to beginning ascension to power operations.
    Date of issuance: May 28, 2008.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: 241, 236.
    Facility Operating License Nos. NPF-35 and NPF-52: Amendments 
revised the licenses and the technical specifications.
    Date of initial notice in Federal Register: February 26, 2008 (73 
FR 10302). The Commission's related evaluation of the amendments is 
contained in a Safety Evaluation dated May 28, 2008.
    No significant hazards consideration comments received: No.
    Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., 
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish, 
Louisiana.
    Date of amendment request: November 15, 2007.
    Brief description of amendment: The amendment removed Surveillance 
Requirement (SR) 3.8.3.6 from the Technical Specifications and 
relocated the requirement to a licensee-controlled document. SR 3.8.3.6 
requires the Emergency Diesel Generator Fuel Oil Storage Tank to be 
drained, sediment removed, and cleaned on a 10-year interval.
    Date of issuance: June 2, 2008.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment No.: 160.
    Facility Operating License No. NPF-47: The amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: December 31, 2007 (72 
FR 74357). The Commission's related evaluation of the amendment is 
contained in a Safety Evaluation dated June 2, 2008.
    No significant hazards consideration comments received: No.
    Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, 
Limerick Generating Station, Units 1 and 2, Montgomery County, 
Pennsylvania.
    Date of application for amendment: June 27, 2007.
    Brief description of amendment: The amendments consist of changes 
to the Technical Specifications of each unit to delete the operability 
and surveillance requirements for the drywell air temperature and 
suppression chamber air temperature. These post-accident monitoring 
instrumentation requirements are being re-located to the Limerick 
Generating Station Technical Requirements Manual.
    Date of issuance: May 29, 2008.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 191 and 152.
    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: September 11, 2007 (72 
FR 51860). The Commission's related evaluation of the amendments is 
contained in a Safety Evaluation dated May 29, 2008.
    No significant hazards consideration comments received: No.
    Nine Mile Point Nuclear Station, LLC, Docket No. 50-410, Nine Mile 
Point Nuclear Station, Unit No. 2, Oswego County, New York.
    Date of application for amendment: May 31, 2007, as supplemented by 
letter dated January 7, 2008.
    Brief description of amendment: The amendment revises the accident 
source term in the design basis radiological consequence analyses in 
accordance with Title 10 of the Code of Federal Regulations (10 CFR) 
Section 50.67. The revised accident source term revision replaces the 
methodology that is based on Technical Information Document (TID)-
14844, ``Calculation of Distance Factors for Power and Test Reactor 
Sites,'' with the alternate source term methodology described in 
Regulatory Guide 1.183, ``Alternative Radiological Source Terms for 
Evaluating Design Basis Accidents at Nuclear Power Reactors,'' with the 
exception that TID-14844 will continue to be used as the radiation dose 
basis for equipment qualification and vital area access.
    Date of issuance: May 29, 2008.
    Effective date: As of the date of issuance to be implemented within 
120 days.
    Amendment No.: 125.
    Renewed Facility Operating License No. DPR-69: Amendment revised 
the License and Technical Specifications.
    Date of initial notice in Federal Register: July 31, 2007 (72 FR 
41786).
    The supplement dated January 7, 2008, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the Nuclear 
Regulatory Commission staff's initial proposed no significant hazards 
consideration determination. The Commission's related evaluation of the 
amendment is contained in a Safety Evaluation dated May 29, 2008.
    No significant hazards consideration comments received: No.

Notice of Issuance of Amendments to Facility Operating Licenses and 
Final Determination of No Significant Hazards Consideration and 
Opportunity for a Hearing (Exigent Public Announcement or Emergency 
Circumstances)

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application for the 
amendment complies with the standards and requirements of the Atomic 
Energy Act of 1954, as amended (the Act), and the Commission's rules 
and regulations. The Commission has made appropriate findings as 
required by the Act and the Commission's rules and regulations in 10 
CFR Chapter I, which are set forth in the license amendment.
    Because of exigent or emergency circumstances associated with the 
date

[[Page 34345]]

the amendment was needed, there was not time for the Commission to 
publish, for public comment before issuance, its usual Notice of 
Consideration of Issuance of Amendment, Proposed No Significant Hazards 
Consideration Determination, and Opportunity for a Hearing.
    For exigent circumstances, the Commission has either issued a 
Federal Register notice providing opportunity for public comment or has 
used local media to provide notice to the public in the area 
surrounding a licensee's facility of the licensee's application and of 
the Commission's proposed determination of no significant hazards 
consideration. The Commission has provided a reasonable opportunity for 
the public to comment, using its best efforts to make available to the 
public means of communication for the public to respond quickly, and in 
the case of telephone comments, the comments have been recorded or 
transcribed as appropriate and the licensee has been informed of the 
public comments.
    In circumstances where failure to act in a timely way would have 
resulted, for example, in derating or shutdown of a nuclear power plant 
or in prevention of either resumption of operation or of increase in 
power output up to the plant's licensed power level, the Commission may 
not have had an opportunity to provide for public comment on its no 
significant hazards consideration determination. In such case, the 
license amendment has been issued without opportunity for comment. If 
there has been some time for public comment but less than 30 days, the 
Commission may provide an opportunity for public comment. If comments 
have been requested, it is so stated. In either event, the State has 
been consulted by telephone whenever possible.
    Under its regulations, the Commission may issue and make an 
amendment immediately effective, notwithstanding the pendency before it 
of a request for a hearing from any person, in advance of the holding 
and completion of any required hearing, where it has determined that no 
significant hazards consideration is involved.
    The Commission has applied the standards of 10 CFR 50.92 and has 
made a final determination that the amendment involves no significant 
hazards consideration. The basis for this determination is contained in 
the documents related to this action. Accordingly, the amendments have 
been issued and made effective as indicated.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these amendments. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.12(b) and has made a determination based on that assessment, 
it is so indicated.
    For further details with respect to the action see (1) the 
application for amendment, (2) the amendment to Facility Operating 
License, and (3) the Commission's related letter, Safety Evaluation 
and/or Environmental Assessment, as indicated. All of these items are 
available for public inspection at the Commission's Public Document 
Room (PDR), located at One White Flint North, Public File Area 01F21, 
11555 Rockville Pike (first floor), Rockville, Maryland. Publicly 
available records will be accessible from the Agencywide Documents 
Access and Management System's (ADAMS) Public Electronic Reading Room 
on the Internet at the NRC Web site, https://www.nrc.gov/reading-rm/