[Federal Register Volume 73, Number 98 (Tuesday, May 20, 2008)]
[Notices]
[Pages 29158-29168]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E8-11246]
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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 April 24 to May 7, 2008. The last biweekly
notice was published on May 6, 2008 (73 FR 25034).
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 T6-D44, 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 O1-F21, 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 O1-F21, 11555 Rockville Pike
(first floor), Rockville, Maryland. Publicly available records will be
accessible from the Agencywide Documents Access and Management System's
(ADAMS) Public Electronic Reading Room on the Internet at the NRC Web
site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request
for a hearing or petition for leave to intervene is filed 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
[[Page 29159]]
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
[email protected], 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 ViewerTM
to access the Electronic Information Exchange (EIE), a component of the
E-Filing system. The Workplace Forms ViewerTM is free and is
available at http://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 http://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 http://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 http://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: 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.
[[Page 29160]]
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
http://ehd.nrc.gov/EHD_Proceeding/home.asp, unless excluded pursuant
to an order of the Commission, 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, http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS
or if there are problems in accessing the documents located in ADAMS,
contact the PDR Reference staff at 1 (800) 397-4209, (301) 415-4737 or
by e-mail to [email protected].
AmerGen Energy Company, LLC, Docket No. 50-461, Clinton Power Station
(CPS), Unit No.1, DeWitt County, Illinois
Date of amendment request: January 26, 2007.
Description of amendment request: The proposed amendment would
revise Technical Specification 3.3.1.1, ``Reactor Protection System
(RPS) Instrumentation,'' Table 3.3.1.1-1, ``Reactor Protection System
Instrumentation,'' Function 8, ``Scram Discharge Volume Water Level--
High,'' item b, ``Float Switch,'' by replacing Surveillance Requirement
(SR) 3.3.1.1.9 with SR 3.3.1.1.12. This change will effectively revise
the surveillance frequency for the scram discharge volume level float
switch from every 92 days to every 24 months.
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 TS change involves a change in the surveillance
frequency for the SDV water level float switch channel functional
test. The proposed TS change does not physically impact the plant.
The proposed change does not affect the design of the SDV water
level instruments, the operational characteristics or function of
the instruments, the interfaces between the instruments and the RPS,
or the reliability of the SDV water level instruments. The proposed
TS change does not degrade the performance of, or increase the
challenges to, any safety systems assumed to function in the
accident analysis. As noted in the Bases to TS 3.3.1.1, even though
the two types of SDV Water Level--High Functions are an input to the
RPS logic, no credit is taken for a scram initiated from these
functions for any of the design basis accidents or transients
evaluated in the CPS Updated Safety Analysis Report (USAR). An
inoperable SDV water level instrument is not considered as an
initiator of any analyzed event. The proposed TS change does not
impact the usefulness of the SRs in evaluating the operability of
required systems and components, or the way in which the
surveillances are performed. In addition, the frequency of
surveillance testing is not considered an initiator of any analyzed
accident, nor does a revision to the frequency introduce any
accident initiators. Therefore, the proposed change does not involve
a significant increase in the probability of an accident previously
evaluated.
The consequences of a previously analyzed event are dependent on
the initial conditions assumed in the analysis, the availability and
successful functioning of equipment assumed to operate in response
to the analyzed event, and the setpoints at which these actions are
initiated. The consequences of a previously evaluated accident are
not significantly increased by the proposed change. The proposed
change does not affect the performance of any equipment credited to
mitigate the radiological consequences of an accident. The risk
assessment of the proposed changes has concluded that there is an
insignificant increase in the core damage frequency as well as the
total population dose rate. Historical review of surveillance test
results and associated maintenance records did not find evidence of
failures that would invalidate the above conclusions.
Therefore, the proposed change does not alter the ability to
detect and mitigate events and, as such, does not involve a
significant increase in the 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 TS change does not introduce any failure mechanisms
of a different type than those previously evaluated, since there are
no physical changes being made to the facility. No new or different
equipment is being installed. No installed equipment is being
operated in a different manner. There is no change being made to the
parameters within which CPS is operated. There are no setpoints at
which protective or mitigative actions are initiated that are
affected by this proposed action. The change does not alter
assumptions made in the safety analysis. This proposed action will
not alter the manner in which equipment operation is initiated, nor
will the function demands on credited equipment be changed. No
alteration in the procedures, which ensure the unit remains within
analyzed limits, is proposed, and no change is being made to
procedures relied upon to respond to an off-normal event. As a
result, no new failure modes are being introduced. The way
surveillance tests are performed remains unchanged. A historical
review of surveillance test results and associated maintenance
records indicated there was no evidence of any failures that would
invalidate the above conclusions.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any [accident]
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
Margins of safety are established in the design of components,
the configuration of components to meet certain performance
parameters, and in the establishment of setpoints to initiate alarms
or actions. The proposed TS change involves a change in the
surveillance frequency for the SDV water level float switch channel
functional test. There is no change in the design of the affected
systems, no alteration of the setpoints at which alarms or actions
are initiated, and no change in plant configuration from original
design. The proposed change does not significantly impact the
condition or performance of structures, systems, and components
relied upon for accident mitigation. The proposed change does not
result in any hardware changes or in any changes to the analytical
limits assumed in accident analyses. Existing operating margin
between plant conditions and actual plant setpoints is not
significantly reduced due to these changes. The proposed change does
not significantly impact any safety analysis assumptions or results.
AmerGen has conducted a risk assessment to determine the impact
of a change to the SDV water level instrument surveillance frequency
from the current once every 92 days to once every 24 months for the
risk measures of Core Damage Frequency (CDF) and Large Early Release
Frequency (LERF). This assessment indicated that the proposed CPS
surveillance frequency extension has a very small change in risk to
the public and is an acceptable plant change from a risk
perspective.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. Bradley J. Fewell, Associate General
Counsel,
[[Page 29161]]
Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL
60555.
NRC Branch Chief: Russell Gibbs.
Carolina Power & Light Company, Docket Nos. 50-325 and 50-324,
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North
Carolina
Date of amendments request: July 17, 2007.
Description of amendment request: The proposed amendment would
modify Brunswick Steam Electric Plant, Units 1 and 2, technical
specifications (TS) requirements regarding control room envelope
habitability in TS 3.7.3, ``Control Room Emergency Ventilation (CREV)
System,'' and TS Section 5.5, ``Programs and Manuals.'' The changes
would be consistent with NRC-approved industry Technical Specifications
Task Force (TSTF) standard TS change traveler, TSTF-448, Revision 3.
The NRC staff issued a ``Notice of Availability of Technical
Specification Improvement to Modify Requirements Regarding Control Room
Envelope Habitability Using the Consolidated Line Item Improvement
Process,'' associated with TSTF-448, Revision 3, in the Federal
Register on January 17, 2007 (72 FR 2022). The notice included a model
safety evaluation, a model no significant hazards consideration (NSHC)
determination, and a model license amendment request. In its
application dated July 17, 2007, Carolina Power and Light Company (the
licensee) affirmed the applicability of the model NSHC determination.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of NSHC is presented below:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change does not adversely affect accident
initiators or precursors nor alter the design assumptions,
conditions, or configuration of the facility. The proposed change
does not alter or prevent the ability of structures, systems, and
components (SSCs) to perform their intended function to mitigate the
consequences of an initiating event within the assumed acceptance
limits. The proposed change revises the TS for the control room
envelope (CRE) emergency ventilation system, which is a mitigation
system designed to minimize unfiltered air leakage into the CRE and
to filter the CRE atmosphere to protect the CRE occupants in the
event of accidents previously analyzed. An important part of the CRE
emergency ventilation system is the CRE boundary. The CRE emergency
ventilation system is not an initiator or precursor to any accident
previously evaluated. Therefore, the probability of any accident
previously evaluated is not increased. Performing tests to verify
the operability of the CRE boundary and implementing a program to
assess and maintain CRE habitability ensure that the CRE emergency
ventilation system is capable of adequately mitigating radiological
consequences to CRE occupants during accident conditions, and that
the CRE emergency ventilation system will perform as assumed in the
consequence analyses of design basis accidents. Thus, the
consequences of any accident previously evaluated are not increased.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident From Any Accident Previously
Evaluated
The proposed change does not impact the accident analysis. The
proposed change does not alter the required mitigation capability of
the CRE emergency ventilation system, or its functioning during
accident conditions as assumed in the licensing basis analyses of
design basis accident radiological consequences to CRE occupants. No
new or different accidents result from performing the new
surveillance or following the new program. The proposed change does
not involve a physical alteration of the plant (i.e., no new or
different type of equipment will be installed) or a significant
change in the methods governing normal plant operation. The proposed
change does not alter any safety analysis assumptions and is
consistent with current plant operating practice. Therefore, this
change does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
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 affect safety
analysis acceptance criteria. The proposed change will not result in
plant operation in a configuration outside the design basis for an
unacceptable period of time without compensatory measures. The
proposed change does not adversely affect systems that respond to
safely shut down the plant and to maintain the plant in a safe
shutdown condition. Therefore, the proposed change does not involve
a significant reduction in a margin of safety.
The NRC staff has reviewed the analysis adopted by the licensee
and, based on this review it appears that the three standards of 10 CFR
50.92(c) are satisfied. Therefore, the NRC staff proposes to determine
that the amendment request involves no significant hazards
consideration.
Attorney for licensee: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Thomas H. Boyce.
Carolina Power & Light Company, et al., Docket No. 50-400, Shearon
Harris Nuclear Power Plant, Unit 1, Wake and Chatham Counties, North
Carolina
Date of amendment request: January 4, 2008.
Description of amendment request: The proposed amendments would
modify technical specification (TS) requirements related to control
room envelope (CRE) habitability in accordance with the U.S. Nuclear
Regulatory Commission (NRC)-approved Revision 3 of Technical
Specification Task Force (TSTF) Standard Technical Specifications (STS)
Change Traveler TSTF-448, ``Control Room Habitability.''
The NRC staff published a notice of opportunity for comment in the
Federal Register on October 17, 2006 (71 FR 61075), on possible license
amendments adopting TSTF-448, which included a model safety evaluation
(SE) and model no significant hazards consideration (NSHC)
determination. The NRC staff subsequently issued a notice of
availability of the models for referencing in license amendment
applications in the Federal Register on January 17, 2007 (72 FR 2022),
which included the resolution of public comments on the model SE and
model NSHC determination. The licensee affirmed the applicability of
the following NSHC determination in its application dated January 4,
2008.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of no significant hazards consideration is presented below:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change does not adversely affect accident
initiators or precursors nor alter the design assumptions,
conditions, or configuration of the facility. The proposed change
does not alter or prevent the ability of structures, systems, and
components (SSCs) to perform their intended function to mitigate the
consequences of an initiating event within the assumed acceptance
limits. The proposed change revises the TS for the CRE emergency
ventilation system, which is a mitigation system designed to
minimize unfiltered air leakage into the CRE and to filter the CRE
atmosphere to protect the CRE occupants in the event of accidents
previously analyzed. An important part of the CRE emergency
ventilation system is the CRE boundary. The CRE emergency
[[Page 29162]]
ventilation system is not an initiator or precursor to any accident
previously evaluated. Therefore, the probability of any accident
previously evaluated is not increased. Performing tests to verify
the operability of the CRE boundary and implementing a program to
assess and maintain CRE habitability ensure that the CRE emergency
ventilation system is capable of adequately mitigating radiological
consequences to CRE occupants during accident conditions, and that
the CRE emergency ventilation system will perform as assumed in the
consequence analyses of design basis accidents. Thus, the
consequences of any accident previously evaluated are not increased.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident From Any Accident Previously
Evaluated
The proposed change does not impact the accident analysis. The
proposed change does not alter the required mitigation capability of
the CRE emergency ventilation system, or its functioning during
accident conditions as assumed in the licensing basis analyses of
design basis accident radiological consequences to CRE occupants. No
new or different accidents result from performing the new
surveillance or following the new program. The proposed change does
not involve a physical alteration of the plant (i.e., no new or
different type of equipment will be installed) or a significant
change in the methods governing normal plant operation. The proposed
change does not alter any safety analysis assumptions and is
consistent with current plant operating practice. Therefore, this
change does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed change does not alter the manner in which safety
limits, limiting safety system settings or limiting conditions for
operation as determined. The proposed change does not affect safety
analysis acceptance criteria. The proposed change will not result in
plant operation in a configuration outside the design basis for an
unacceptable period of time without compensatory measures. The
proposed change does not adversely affect systems that respond to
safely shut down the plant and to maintain the plant in a safe
shutdown condition. Therefore, the proposed change does not involve
a significant reduction in a margin of safety.
The NRC staff proposes to determine that the amendment request
involves no significant hazards consideration.
Attorney for licensee: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Thomas H. Boyce.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457,
Braidwood Station, Units 1 and 2, Will County, Illinois
Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455,
Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois
AmerGen Energy Company, LLC, Docket No. 50-461, Clinton Power Station,
Unit No. 1, DeWitt County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden
Nuclear Power Station, Units 2 and 3, Grundy County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle
County Station, Units 1 and 2, LaSalle County, Illinois
Exelon Generation Company, LLC, Docket No. 50-352 and No. 50-353,
Limerick Generating Station, Unit 1 and 2, Montgomery County,
Pennsylvania
AmerGen Energy Company, LLC, et al., Docket No. 50-219, Oyster Creek
Nuclear Generating Station, Ocean County, New Jersey
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3,York
and Lancaster Counties, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad
Cities Nuclear Power Station, Units 1 and 2, Rock Island County,
Illinois
AmerGen Energy Company, LLC, Docket No. 50-289, Three Mile Island
Nuclear Station, Unit 1 (TMI-1), Dauphin County, Pennsylvania
Date of amendment request: February 28, 2008.
Description of amendment request: The proposed amendment would
clarify the wording of the Radioactive Effluent Controls Program (RECP)
administrative technical specifications to reflect the intent of
Generic Letter 89-01, ``Implementation of Programmatic Controls for
Radiological Effluent Technical Specifications [TS] in the
Administrative Controls Section of the Technical Specifications and the
Relocation of Procedural Details of RETS to the Offsite Dose
Calculation Manual or to the Process Control Program,'' regarding the
determination requirements for cumulative and projected dose
contributions. The proposed change will address ambiguity in the
current TS where the program element could be interpreted to require
determining projected dose contributions for the calendar quarter and
current calendar year every 31 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 change involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
The proposed change revises the applicable TS Section to conform
to TSTF-308-A, Revision 1[, ``Determination of Cumulative and
Projected Dose Contributions in RECP.'']
The proposed change is administrative and simply provides
enhanced clarity of current requirements. Therefore, this change
does not affect any accident initiators, does not affect the ability
to successfully respond to previously evaluated accidents, and does
not affect radiological assumptions used in the evaluations. This
change will not alter the operation of process variables,
structures, systems, or components as described in the affected
stations' Updated Final Safety Analysis Report (UFSAR). As such, the
probability of occurrence for a previously evaluated accident is not
increased.
The consequences of a previously analyzed event are dependent on
the initial conditions assumed in the analysis, the availability and
successful functioning of equipment assumed to operate in response
to the analyzed event, and the setpoints at which these actions are
initiated. The consequences of a previously evaluated accident are
not increased by the proposed change. The proposed change does not
affect the performance of any equipment credited to mitigate the
radiological consequences of an accident.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the change create the possibility of a new or different
kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not involve a physical alteration of
the plant (i.e., no new or different type of equipment will be
installed) or changes in methods governing normal plant operation.
No system or component setpoints will be changed, and the proposed
change will not impose any new or eliminate any old requirements.
There are no new accident initiators or equipment failure modes
resulting from the proposed changes. The proposed changes are
administrative in nature and support the implementation of common
programs.
Thus, this proposed change does not create the possibility of a
new or different kind of accident from any previously evaluated.
3. Does the change involve a significant reduction in a margin
of safety?
Response: No.
The proposed change revises the applicable TS Section for the
affected EGC and AmerGen stations to provide clarity concerning the
determination requirements
[[Page 29163]]
for cumulative and projected dose contributions.
The proposed change is administrative in nature and does not
modify the safety limits or setpoints at which protective actions
are initiated, and does not change the requirements governing
operation or availability of safety equipment assumed to operate to
preserve the margin of safety. In addition, there are no changes
proposed to equipment operability requirements, setpoints, or
limiting parameters specified in the stations' Technical
Specifications.
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
requested amendments involve no significant hazards consideration.
Attorney for licensee: Mr. Bradley Fewell, Associate General
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road,
Warrenville, IL 60555.
NRC Branch Chief: Russell Gibbs.
Florida Power Corporation, et al., Docket No. 50-302, Crystal River
Unit 3 Nuclear Generating Plant, Citrus County, Florida
Date of amendment request: July 12, 2007.
Description of amendment request: The proposed amendment would
modify Crystal River Unit 3 Improved Technical Specifications (ITS)
requirements related to control room envelope habitability in ITS
Section 3.7.12, ``Control Room Emergency Ventilation System (CREVS),''
and ITS Section 5.6.2.21, ``Control Complex Habitability Envelope
Integrity Program.'' The changes would be consistent with the NRC-
approved industry Technical Specifications Task Force (TSTF) standard
TS change traveler, TSTF-448, Revision 3. The NRC staff issued a
``Notice of Availability of Technical Specification Improvement to
Modify Requirements Regarding Control Room Envelope Habitability Using
the Consolidated Line Item Improvement Process,'' associated with TSTF-
448, Revision 3, in the Federal Register on January 17, 2007 (72 FR
2022). The notice included a model safety evaluation, a model no
significant hazards consideration (NSHC) determination, and a model
license amendment request. In its application dated July 12, 2007,
Florida Power Corporation (the licensee) affirmed the applicability of
the model NSHC determination.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of NSHC is presented below:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change does not adversely affect accident
initiators or precursors nor alter the design assumptions,
conditions, or configuration of the facility. The proposed change
does not alter or prevent the ability of structures, systems, and
components (SSCs) to perform their intended function to mitigate the
consequences of an initiating event within the assumed acceptance
limits. The proposed change revises the TS for the control room
envelope (CRE) emergency ventilation system, which is a mitigation
system designed to minimize unfiltered air leakage into the CRE and
to filter the CRE atmosphere to protect the CRE occupants in the
event of accidents previously analyzed. An important part of the CRE
emergency ventilation system is the CRE boundary. The CRE emergency
ventilation system is not an initiator or precursor to any accident
previously evaluated. Therefore, the probability of any accident
previously evaluated is not increased. Performing tests to verify
the operability of the CRE boundary and implementing a program to
assess and maintain CRE habitability ensure that the CRE emergency
ventilation system is capable of adequately mitigating radiological
consequences to CRE occupants during accident conditions, and that
the CRE emergency ventilation system will perform as assumed in the
consequence analyses of design basis accidents. Thus, the
consequences of any accident previously evaluated are not increased.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident From Any Accident Previously
Evaluated
The proposed change does not impact the accident analysis. The
proposed change does not alter the required mitigation capability of
the CRE emergency ventilation system, or its functioning during
accident conditions as assumed in the licensing basis analyses of
design basis accident radiological consequences to CRE occupants. No
new or different accidents result from performing the new
surveillance or following the new program. The proposed change does
not involve a physical alteration of the plant (i.e., no new or
different type of equipment will be installed) or a significant
change in the methods governing normal plant operation. The proposed
change does not alter any safety analysis assumptions and is
consistent with current plant operating practice. Therefore, this
change does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
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 affect safety
analysis acceptance criteria. The proposed change will not result in
plant operation in a configuration outside the design basis for an
unacceptable period of time without compensatory measures. The
proposed change does not adversely affect systems that respond to
safely shut down the plant and to maintain the plant in a safe
shutdown condition. Therefore, the proposed change does not involve
a significant reduction in a margin of safety.
The NRC staff has reviewed the analysis adopted by the licensee
and, based on this review it appears that the three standards of 10 CFR
50.92(c) are satisfied. Therefore, the NRC staff proposes to determine
that the amendment request involves no significant hazards
consideration.
Attorney for licensee: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Thomas H. Boyce.
Florida Power Corporation, et al., Docket No. 50-302, Crystal River
Unit 3 Nuclear Generating Plant, Citrus County, Florida
Date of amendment request: January 17, 2008.
Description of amendment request: The proposed amendment would
revise the Crystal River Unit 3 (CR3) Improved Technical Specification
SR [surveillance requirement] 3.7.5.2, ``Emergency Feedwater System,''
and would align the text for the surveillance test frequency with the
text in the NRC technical report, NUREG-1430, Volume 1, Revision 3,
``Standard Technical Specifications Babcock and Wilcox Plants-
Specifications.''
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 not involve a significant increase in the probability or
consequences of an accident previously evaluated.
Changing the test frequency of SR 3.7.5.2 from ``45 days on a
STAGGERED TEST BASIS'' to ``In accordance with the Inservice Testing
Program'' will not affect any CR3 structure, system or component
(SSC). As such, there will be no effect on plant operation, to any
design function or analysis that verifies the capability of a SSC to
perform a design function, or to any of the
[[Page 29164]]
previously evaluated accidents in the CR3 Final Safety Analysis
Report (FSAR). The proposed amendment will not change any operating
procedure or administrative control.
Since the proposed amendment does not involve a change to any
SSC, their operation or design, and since the proposed amendment
will not change any of the previously evaluated accident in the CR3
FSAR, the probability and consequences of any accident or operating
scenario will be unchanged by its implementation.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
The proposed change will 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 change will not alter any assumptions made
in the safety analysis.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does not involve a significant reduction in a margin on
safety.
The proposed change will 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 this change. The proposed change will not result
in plant operation in a configuration outside of the accepted design
basis. As such, 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: David T. Conley, Associate General Counsel
II--Legal Department, Progress Energy Service Company, LLC, Post Office
Box 1551, Raleigh, North Carolina 27602.
NRC Branch Chief: Thomas H. Boyce.
Tennessee Valley Authority (TVA), Docket Nos. 50-327 and 50-328,
Sequoyah Nuclear Plant, Units 1 and 2, Hamilton County, Tennessee
Date of amendment request: April 15, 2008.
Description of amendment request: The proposed amendment would
change and realign several containment isolation subject matter
Technical Specifications to the Nuclear Regulatory Commission
Regulation (NUREG)--1431, Revision 3, ``Standard Technical
Specifications Westinghouse Plants.''
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.
TVA's proposed change that involves administrative changes,
including relocation of actions or SRs [surveillance requirements]
to another LCO [limiting condition of operation] or to the TS
administrative controls section; revision of text to conform with
NUREG-1431 and add clarity; minor revision to definitions and other
LCOs for fidelity; and deletion of Type A leakage test performance
deferral information, do not result in technical changes to
requirements currently present in the TS. These changes are
administrative in nature and do not impact initiators of analyzed
events.
They also do not impact the assumed mitigation of accidents or
transients events. Therefore, these changes do not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
TVA's proposed change eliminates an hourly time limit for
operation of the containment purge supply and exhaust isolation
valves. This change also eliminates associated actions and SRs. The
containment purge and ventilation system is qualified and designed
to isolate in the event of a design basis accident (DBA). The
probability of occurrence of an accident is not increased by
deletion of the time limit nor will it affect the system's
capability for purge valve closure or containment isolation. This
change does not result in a modification of the reactor building
purge ventilation (RBPV) system. Consequently, the 10 CFR 100 limits
for site boundary dose will not be exceeded in the event of an
accident during containment purge operation. Therefore, the proposed
amendment does not involve a significant increase in the probability
or consequences of an accident previously evaluated.
TVA proposes to implement a new required action for systems that
meet the criteria of general design requirement (GDC) 57 for closed
system. The change would provide relaxation of the completion time
for isolation of a penetration flow path for the identified systems.
This change does not result in any plant modification and therefore
the systems will continue to mitigate the consequences of a DBA. The
proposed completion time is reasonable and is consistent with
standard industry guidelines to ensure the accident mitigation
equipment will be restored in a timely manner. The allow[ed]
completion time for isolation is not a precursor to any DBE [Design
Basis Event]; thus, no increase in the probability of accident
previously evaluated is considered. Therefore, the proposed change
does not involve a significant increase in the probability or
consequences of an accident previously evaluated.
TVA's proposed change reduces the amount of technical details of
an SR and relocates it to a licensee controlled document under the
control of 10 CFR 50.59. The reduction in information is consistent
with NUREG-1431. This change does not result in any hardware or
operating procedure changes. Requirements to perform surveillances
of the systems detailed in the information are not eliminated. The
details being removed from the TSs are not assumed to be an
initiator of any analyzed event and therefore would not involve a
significant increase in the probability of an accident. This
information also does not impact the assumed mitigation of accidents
or transient events. Therefore, these changes do not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
TVA's proposed change adds a more restrictive requirement to
conform to NUREG-1431 in support of eliminating the hourly time
limit for the operation of the containment purge isolation valves.
This change will require a verification that open travel restrictors
are in the containment purge valves during modes of applicability.
The change will also require conditional leakage testing of a
containment purge valve used to isolate a penetration.
This change does not result in a modification of the RBPV system
as the restrictors were installed during initial plant licensing.
Leakage testing is not a new requirement for these valves. These
changes provide a more stringent requirement that previously existed
in the TSs. These more stringent requirements do not result in
operation that will increase the probability of initiating an
analyzed event. This change assists in the operability of the
containment purge supply and exhaust isolation valves.
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.
TVA's proposed changes that involve administrative change,
including relocation of actions or SRs to another LCO or to the TS
administrative controls section; revision of text to conform with
NUREG-1431 and add clarity; minor revision to definitions and other
LCOs for fidelity; and deletion of Type A leakage test performance
deferral information, do not result in technical changes to
requirements currently present in the TS. These changes do not
involve a physical alteration of the plant (no new or different type
of equipment will be installed) or changes in the methods governing
normal plant operations. These changes will not impose any new or
different requirements or eliminate any existing requirements.
Therefore, this change does not create the possibility of a new or
different kind of accident from any accident previously evaluated.
TVA's proposed change eliminates an hourly time limit for
operation of the containment purge supply and exhaust
[[Page 29165]]
isolation valves. This change also eliminates associated actions and
SRs. This change does not involve a change to plant systems,
components, or operating practices that could result in a change in
accident generation potential. The containment purge supply and
exhaust valves are utilized for the isolation of flow paths to the
environs and are not a feature that could generate a postulated
accident. Elimination of the operational time restriction of the
containment purge supply and exhaust isolation valves will not
impact the potential for accidents. Therefore, this proposed change
does not create the possibility of a new or different kind of
accident from any previously evaluated.
TVA proposes to implement a new required action for systems that
meet the closed system design. The change would provide relaxation
of the completion time for isolation of a penetration flow path for
the identified systems. This change does not involve a physical
alteration of the plant (no new or different type of equipment will
be installed) or require any unusual operator actions. The proposed
change will not alter the way any structure, system, or component
functions, and will not alter the manner the plant is operated. The
response of the plant and the operators following an accident will
not be different. The change does not introduce any new failure
modes.
Therefore, this proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
TVA's proposed change reduces the amount of technical details of
an SR and relocates it to a licensee controlled document under the
control of 10 CFR 50.59.
The reduction in information is consistent with NUREG-1431 and
adequate control of the information will be maintained. This change
does not involve a physical alteration of the plant (no new or
different type of equipment will be installed) or changes in testing
requirements of these systems. This change will not alter
assumptions made in the safety analysis and licensing basis.
Therefore, this proposed change does not create the possibility of a
new or different kind of accident from any previously evaluated.
TVA's proposed change adds a more restrictive requirement to
conform to NUREG-1431 in support of eliminating the hourly time
limit for the operation of the containment purge isolation valves.
This change will require a verification that open travel restrictors
are in the containment purge valves during modes of applicability.
The change will also require conditional leakage testing of a
containment purge valve used to isolate a penetration. This change
does not result in a modification of the RBPV system as the
restrictors were installed during initial plant licensing. Leakage
testing is not a new requirement for these valves. Verification of
restrictors does not modify normal plant operations, but does impose
different administrative requirements. Action required leakage rate
testing of an isolated containment purge valve does create new
requirements. However, these changes will maintain the assumptions
in the safety analyses and licensing basis. Therefore, this 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.
TVA's proposed changes that involve administrative change,
including relocation of actions or SRs to another LCO or to the TS
administrative controls section; revision of text to conform with
NUREG-1431 and add clarity; minor revision to definitions and other
LCO for fidelity; and deletion of Type A leakage test performance
deferral information, do not result in technical changes to
requirements currently present in the TS. These changes will not
reduce a margin of safety because it has no impact on any safety
analysis assumptions. Also, since these changes are administrative
in nature, no question of safety is involved. Therefore, these
changes do not involve a significant reduction in a margin of
safety.
TVA's proposed change eliminates an hourly time limit for
operation of the containment purge supply and exhaust isolation
valves. This change also eliminates associated actions and SRs. The
proposed change does not alter plant systems or their setpoints that
are used to maintain the margin of safety. Operability will continue
to be maintained by testing and verification requirements on the
containment purge valves. Therefore, the proposed change does not
involve a reduction in a margin of safety.
TVA proposes to implement a new required action for systems that
meet the closed system design. The change would provide relaxation
of the completion time for isolation of a penetration flow path for
the identified systems. This change does not result in any plant
modification, testing requirements to ensure operability, or a
change in safety limits or safety system settings. The proposed
completion time is reasonable and is consistent with standard
industry guidelines to ensure the accident mitigation equipment will
be restored in a timely manner. Therefore, the proposed change does
not involve a reduction in a margin of safety.
TVA's proposed change reduces the amount of technical details of
an SR and relocates it to a licensee controlled document under the
control of 10 CFR 50.59. This change does not reduce the margin of
safety since the location of the details has no impact on any safety
assumptions. Therefore, the proposed change does not involve a
reduction in a margin of safety.
TVA's proposed change adds a more restrictive requirement to
conform to NUREG-1431 in support of eliminating the hourly time
limit for the operation of the containment purge isolation valves.
This change will require a verification that open travel restrictors
are in the containment purge valves during modes of applicability.
The change will also require conditional leakage testing of a
containment purge valve used to isolate a penetration. Adding more
stringent requirements, by definition, provides additional
restrictions to enhance plant safety. As such, no question of safety
is involved. 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: General Counsel, Tennessee Valley Authority,
400 West Summit Hill Drive, ET 11A, Knoxville, Tennessee 37902.
NRC Branch Chief: Thomas H. Boyce.
Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281,
Surry Power Station, Unit Nos. 1 and 2, Surry County, Virginia
Date of amendment request: April 2, 2008.
Description of amendment request: The proposed change revises
Technical Specification (TS) Section 5.0, ``Design Features,'' to
delete certain design details and descriptions included in TS 5.0 that
are already contained in the Updated Final Safety Analysis Report
(UFSAR), or are redundant to existing TS requirements, and are not
required to be included in the TSs pursuant to Title 10 of the Code of
Federal Regulations (10 CFR), Part 50, Section 50.36(c)(4). The
proposed change also revises the format of, and incorporates design
descriptions into, TS 5.0 consistent with Nuclear Regulatory Commission
(NRC) policy and NUREG-1431, Standard Technical Specifications,
Westinghouse Plants, Revision 3.0, to the extent practical. An
editorial change is also proposed to address a minor TS discrepancy
introduced by a previous license amendment.
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 change involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to Section 5.0, ``Design Features,'' deletes
certain details from the TS that are not required to be maintained
in the TS by 10 CFR 50.36(c)(4), adds new TS limits that meet the 10
CFR 50.36(c)(4) inclusion criteria and revises the TS for
consistency with NUREG-1431, Revision 3.0. The remaining change
addresses a minor editorial discrepancy.
The proposed change does not add or modify any plant system,
structures or component and has no impact on plant equipment
operation. Thus, the proposed change is administrative in nature and
does
[[Page 29166]]
not affect initiators of analyzed events or assumed mitigation of
accident or transient events. Therefore, this change does not
involve a significant increase in the probability or consequences of
an accident previously evaluated.
2. Does the change create the possibility of a new or different
kind of accident from any accident previously evaluated?
Response: No.
Since the proposed change is administrative in nature, it does
not involve a physical alteration of the plant (no new or different
type of equipment will be installed) or changes in methods governing
normal plant operation. The proposed change does not adversely
affect accident initiators or precursors nor alter the design
assumptions, conditions, or configuration of the facility. The
proposed change does not alter or prevent the ability of structures,
systems, and components (SSCs) to perform their intended function to
mitigate the consequences of an initiating event within the assumed
acceptance limits. Thus, this change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does this change involve a significant reduction in a margin
of safety?
Response: No.
The proposed TS change is administrative in nature and as such
does not alter the manner in which safety limits, limiting safety
system settings or limiting conditions for operation are determined,
and the dose analysis acceptance criteria are not affected. The
proposed change does not result in plant operation in a
configuration outside the analyses or design basis and does not
adversely affect systems that respond to safely shut down the plant
and to maintain the plant in a safe shutdown condition. Therefore,
the proposed TS 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: Lillian M. Cuoco, Esq., Senior Counsel,
Dominion Resources Services, Inc., 120 Tredegar Street, RS-2 Richmond,
VA 23219.
NRC Branch Chief: Melanie C. Wong.
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, http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there
are problems in accessing the documents located in ADAMS, contact the
PDR Reference staff at 1 (800) 397-4209, (301) 415-4737 or by e-mail to
[email protected].
AmerGen Energy Company, LLC, et al., Docket No. 50-219, Oyster Creek
Nuclear Generating Station, Ocean County, New Jersey
Date of application for amendment: April 12, 2007.
Brief description of amendment: The amendment establishes more
effective and appropriate action, surveillance, and administrative
requirements related to ensuring the habitability of the control room
envelope in accordance with Nuclear Regulatory Commission approved
Technical Specification Task Force (TSTF) Standard Technical
Specification change traveler TSTF-448, Revision 3, ``Control Room
Habitability.''
Date of Issuance: April 30, 2008.
Effective date: As of its date of issuance and shall be implemented
within 180 days of issuance.
Amendment No.: 265.
Facility Operating License No. DPR-16: Amendment revised the
License and Technical Specifications.
Date of initial notice in Federal Register: The January 23, 2008,
letter provided clarifying information within the scope of the original
application and did not change the staff's initial proposed no
significant hazards consideration determination dated June 5, 2007 (72
FR 31100). The Commission's related evaluation of this amendment is
contained in a Safety Evaluation dated April 30, 2008.
No significant hazards consideration comments received: No.
Calvert Cliffs Nuclear Power Plant, Inc., Docket Nos. 50-317 and 50-
318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert
County, Maryland
Date of application for amendments: November 8, 2007, as
supplemented by letter dated March 11, 2008.
Brief description of amendments: The amendments modify Technical
Specification (TS) 1.1, ``Definitions,'' to clarify the definitions of
Channel Calibration and Channel Functional Test. The amendments
incorporate TS Task Force (TSTF) Standard TS Change Traveler TSTF-205-
A, ``Revision of Channel Calibration, Channel Functional Test, and
Related Definitions,'' Revision 3, dated July 31, 2003.
Date of issuance: April 23, 2008.
Effective date: As of the date of issuance to be implemented within
60 days.
Amendment Nos.: 286 and 263.
Renewed Facility Operating License Nos. DPR-53 and DPR-69:
Amendments revised the License and Technical Specifications.
Date of initial notice in Federal Register: December 18, 2007 (72
FR 71705).
The letter dated March 11, 2008, 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 these amendments is contained in a Safety Evaluation dated April 23,
2008.
No significant hazards consideration comments received: No.
[[Page 29167]]
Carolina Power & Light Company, Docket Nos. 50-325 and 50-324,
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North
Carolina
Date of application for amendments: September 26, 2007, as
supplemented by letter dated December 7, 2007.
Brief description of amendments: The amendments revise Technical
Specification (TS) 5.5.6, ``Inservice Testing Program,'' to reflect
changes to the American Society of Mechanical Engineers Boiler and
Pressure Vessel Code requirements for inservice testing of pumps and
valves, and corresponding changes to Title 10 of the Code of Federal
Regulations (10 CFR), Section 50.55a, ``Codes and standards.'' The
changes are based on Technical Specification Task Force (TSTF) Traveler
TSTF-479, ``Changes to Reflect Revision of 10 CFR 50.55a,'' as modified
by TSTF-497, ``Limit Inservice Testing Program SR [Surveillance
Requirement] 3.0.2 Application to Frequencies of 2 Years or Less.''
Date of issuance: April 23, 2008.
Effective date: Date of issuance, to be implemented within 60 days.
Amendment Nos.: 247 and 275.
Facility Operating License Nos. DPR-71 and DPR-62: Amendments
change the TSs and licenses.
Date of initial notice in Federal Register: January 29, 2008 (73 FR
5217). The staff's proposed no significant hazards consideration
determination, as published in the Federal Register was based on the
letter dated December 7, 2007. The Commission's related evaluation of
the amendments is contained in a Safety Evaluation dated April 23,
2008.
No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, et al., Docket No. 50-440, Perry
Nuclear Power Plant, Unit No. 1, Lake County, Ohio
Date of application for amendment: September 18, 2007.
Brief description of amendment: This amendment would modify
Technical Specification (TS) requirements related to control room
envelope habitability in accordance with Technical Specification Task
Force (TSTF) Traveler TSTF-448, Revision 3.
Date of issuance: April 25, 2008.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment No.: 148.
Facility Operating License No. NPF-58: This amendment revised the
Technical Specifications and License.
Date of initial notice in Federal Register: January 29, 2008 (73 FR
5221). The Commission's related evaluation of the amendment is
contained in a Safety Evaluation dated April 25, 2008.
No significant hazards consideration comments received: No.
Florida Power Corporation, et al., Docket No. 50-302, Crystal River
Unit No. 3 Nuclear Generating Plant, Citrus County, Florida
Date of application for amendment: April 13, 2007, as supplemented
by letters dated September 4 and 13, 2007, and February 25, 2008.
Brief description of amendment: The amendment changes the technical
specifications (TSs) to extend the completion time associated with an
inoperable low pressure injection train, reactor building spray train,
decay heat closed cycle cooling water train, and decay heat seawater
train, from 72 hours to 7 days. The change has been requested
consistent with NRC-approved T-S Task Force (TSTF) traveler TSTF-430
Revision 2. Additional changes to the TSs implement TSTF-439 Revision
2, to eliminate second completion times.
Date of issuance: April 30, 2008.
Effective date: Date of issuance, to be implemented within 60 days.
Amendment No.: 229.
Facility Operating License No. DPR-72: Amendment revises the
technical specifications.
Date of initial notice in Federal Register: September 12, 2007 (72
FR 52167). The supplements dated September 4 and 13, 2007, and February
25, 2008, 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 30, 2008.
No significant hazards consideration comments received: No.
FPL Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit No.
1, Rockingham County, New Hampshire
Date of amendment request: March 7, 2008, as supplemented by letter
dated March 26, 2008.
Description of amendment request: The amendment revises the
Seabrook Technical Specifications to extend the time allowed to collect
initial plateau curves for the intermediate and power range neutron
detectors to 24 hours after reaching 100 percent of rated thermal
power.
Date of issuance: April 29, 2008.
Effective date: As of its date of issuance, and shall be
implemented within 5 days.
Amendment No.: 118.
Facility Operating License No. NPF-86: The amendment revised the
License and Technical Specifications.
Date of initial notice in Federal Register: March 19, 2008 (73 FR
14850). A correction to the notice was published on March 27, 2008 (73
FR 16327) and a duplicate, bi-weekly notice was published on April 8,
2008 (73 FR 19111). The licensee's March 26, 2008, supplement provided
clarifying information that did not change the scope of the proposed
amendment as described in the original notice of proposed action
published in the Federal Register, and did not change the initial
proposed no significant hazards consideration determination. The
Commission's related evaluation of the amendment is contained in a
Safety Evaluation dated April 29, 2008.
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant, Units 1 and 2 (DCCNP-1 and DCCNP-2), Berrien
County, Michigan
Date of application for amendments: July 30, 2007, as supplemented
by letter dated February 13, 2008.
Brief description of amendments: The amendments added a
Surveillance Requirement, SR 3.8.2.2, that is applicable when offsite
electrical power is supplied to a unit via backfeed through the main
transformer and the unit is in either MODE 5, MODE 6, or during
movement of irradiated fuel.
Date of issuance: April 28, 2008.
Effective date: As of the date of issuance, and shall be
implemented within 45 days.
Amendment No.: 304 (for DCCNP-1) and 287 (for DCCNP-2).
Facility Operating License Nos. DPR-58 and DPR-74: Amendments
revised the Renewed Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: September 25, 2007 (72
FR 54475).
The supplemental letter contained clarifying information, did not
change the initial no significant hazards consideration determination,
and did not expand the scope of the original Federal Register notice.
The Commission's related evaluation of the amendment is contained in a
safety evaluation dated April 28, 2008.
[[Page 29168]]
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald
C. Cook Nuclear Plant, Units 1 and 2 (DCCNP-1 and DCCNP-2), Berrien
County, Michigan
Date of application for amendments: June 13, 2007, as supplemented
by letter dated February 13, 2008.
Brief description of amendments: The amendments revised Section
5.5.9, ``Ventilation Filter Testing Program (VFTP),'' changing the
specified pressure drop values for the combined high efficient
particulate air filters and charcoal adsorbers for three engineered
safety feature ventilation systems from less than 6 inches water gauge
to less than 4 inches water gauge at the specified flow rates.
Date of issuance: April 28, 2008.
Effective date: As of the date of issuance, and shall be
implemented within 45 days.
Amendment No.: 305 (for DCCNP-1) and 288 (for DCCNP-2).
Facility Operating License Nos. DPR-58 and DPR-74: Amendments
revised the Renewed Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: August 14, 2007 (72 FR
45458). The supplemental letter contained clarifying information, did
not change the initial no significant hazards consideration
determination, and did not expand the scope of the original Federal
Register notice. The Commission's related evaluation of the amendment
is contained in a safety evaluation dated April 28, 2008.
No significant hazards consideration comments received: No.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station,
Unit No. 1, Washington County, Nebraska
Date of amendment requests: July 30 and October 19, 2007, as
supplemented by letters dated August 31 and December 12, 2007, and
February 21, March 28, and April 4 and 10, 2008.
Brief description of amendment: The amendment revised Technical
Specification (TS) Limiting Condition for Operation (LCO) 2.4,
``Containment Cooling,'' LCO 2.14, ``Engineered Safety Features System
Initiation Instrumentation Settings,'' and LCO 2.15, ``Instrumentation
and Control Systems''; TS Surveillance Requirement (SR) 3.1,
``Instrumentation and Control,'' SR 3.5(4), ``Containment Isolation
Valves Leak Rate Tests (Type C Tests),'' and SR 3.6(3), ``Containment
Recirculating Air Cooling and Filtering System''; and associated TS
Basis documents and Updated Safety Analysis Report sections to modify
the containment spray system actuation logic to preclude automatic
start of the containment spray pumps for a loss-of-coolant accident.
The amendment also revised TS SR 3.6(3)a. to delete SRs for testing of
the containment air cooling and filtering system emergency mode dampers
and replace it with a surveillance to verify that the dampers are in
the accident positions in all operating plant modes and deletes the
requirement in TS SR 3.6(3)b. to remotely operate dampers. The
amendment added license conditions related to the replacement and
testing of containment air cleaning and filtering (CACF) unit HEPA
(high-efficiency particulate air) filters and surveillance testing of
the CACF unit relief ports. The license conditions require
administrative controls pending the completion of detailed analysis and
confirm commitments for the licensee to submit TS amendments by October
31, 2008.
Date of issuance: May 2, 2008.
Effective date: The license amendment is effective as of its date
of issuance and shall be implemented prior to startup from the 2008
refueling outage.
Amendment No.: 255.
Renewed Facility Operating License No. DPR-40: The amendment
revised the Technical Specifications and added additional conditions to
the Renewed Facility Operating License.
Date of initial notice in Federal Register: August 28, 2007 (72 FR
49581), and January 29, 2008 (73 FR 5227). The supplemental letters
dated August 31 and December 12, 2007, and February 21, March 28, and
April 4 and 10, 2008, provided additional information that clarified
the applications, did not expand the scope of the applications 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 May 2, 2008.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 9th day of May 2008.
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E8-11246 Filed 5-19-08; 8:45 am]
BILLING CODE 7590-01-P