Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, 8068-8076 [E8-2143]
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8068
Federal Register / Vol. 73, No. 29 / Tuesday, February 12, 2008 / Notices
Dated: February 5, 2008.
P. Diane Rausch,
Advisory Committee Management Officer,
National Aeronautics and Space
Administration.
[FR Doc. E8–2513 Filed 2–11–08; 8:45 am]
BILLING CODE 7510–13–P
NUCLEAR REGULATORY
COMMISSION
Biweekly Notice; Applications and
Amendments to Facility Operating
Licenses Involving No Significant
Hazards Considerations
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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 January 17,
2008, to January 30, 2008. The last
biweekly notice was published on (73
FR 5215).
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
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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 60day 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 6D22, 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
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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
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
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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-
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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 https://www.nrc.gov/sitehelp/e-submittals/install-viewer.html.
Information about applying for a digital
ID certificate is available on NRC’s
public website at https://www.nrc.gov/
site-help/e-submittals/applycertificates.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 website 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
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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 firstclass 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 email to
pdr@nrc.gov.
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AmerGen Energy Company, LLC, Docket
No. 50–461, Clinton Power Station, Unit
No.1, DeWitt County, Illinois
Date of amendment request: June 21,
2007.
Description of amendment request: A
change is proposed to the technical
specifications (TSs) of Clinton Power
Station, Unit No. 1 (CPS), consistent
with TS Task Force (TSTF) change
TSTF–423 to the standard technical
specifications (STSs) for boiling-water
reactor (BWR) plants to allow, for some
systems, entry into hot shutdown rather
than cold shutdown to repair
equipment, if risk is assessed and
managed consistent with the program in
place for complying with the
requirements of Title 10 of the Code of
Federal Regulations (10 CFR) Section
50.65(a)(4). The proposed amendment
would modify the TS to risk-informed
requirements regarding selected
required action end states provided in
TSTF–423, Revision 0, ‘‘Technical
Specification End States, NEDC–32988–
A.’’
The CPS has reviewed the proposed
no significant hazards consideration
(NSHC) determination published on
March 23, 2006, (71 FR 14743) as part
of the consolidated line item
improvement process and, based on this
review, it appears that the three
standards of 10 CFR 50.92(c) are
satisfied. The licensee has affirmed the
applicability of the following NSHC
determination in its application.
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 allows a change to
certain required end states when the TS
Completion Times for remaining in power
operation will be exceeded. Most of the
requested technical specification (TS)
changes are to permit an end state of hot
shutdown (Mode 3) rather than an end state
of cold shutdown (Mode 4) contained in the
current TS. The request was limited to: (1)
Those end states where entry into the
shutdown mode is for a short interval, (2)
entry is initiated by inoperability of a single
train of equipment or a restriction on a plant
operational parameter, unless otherwise
stated in the applicable technical
specification, and (3) the primary purpose is
to correct the initiating condition and return
to power operation as soon as is practical.
Risk insights from both the qualitative and
quantitative risk assessments were used in
specific TS assessments. Such assessments
are documented in Section 6 of GE NEDC–
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32988, Revision 2, ‘‘Technical Justification to
Support Risk Informed Modification to
Selected Required Action End States for BWR
Plants.’’ They provide an integrated
discussion of deterministic and probabilistic
issues, focusing on specific technical
specifications, which are used to support the
proposed TS end state and associated
restrictions. The [NRC] staff finds that the
risk insights support the conclusions of the
specific TS assessments. Therefore, the
probability of an accident previously
evaluated is not significantly increased, if at
all. The consequences of an accident after
adopting proposed TSTF–423, are no
different than the consequences of an
accident prior to adopting TSTF–423.
Therefore, the consequences of an accident
previously evaluated are not significantly
affected by this change. The addition of a
requirement to assess and manage the risk
introduced by this change will further
minimize possible concerns. Therefore, this
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 Previously
Evaluated.
The proposed change does not involve a
physical alteration of the plant (no new or
different type of equipment will be installed).
If risk is assessed and managed, allowing a
change to certain required end states when
the TS Completion Times for remaining in
power operation are exceeded, i.e., entry into
hot shutdown rather than cold shutdown to
repair equipment, will not introduce new
failure modes or effects and will not, in the
absence of other unrelated failures, lead to an
accident whose consequences exceed the
consequences of accidents previously
evaluated. The addition of a requirement to
assess and manage the risk introduced by this
change and the commitment by the licensee
to adhere to the guidance in TSTF–IG–05–02,
Implementation Guidance for TSTF–423,
Revision 0, ‘‘Technical Specifications End
States, NEDC–32988–A,’’ will further
minimize possible concerns. Thus, this
change does not create the possibility of a
new or different kind of accident from an
accident previously evaluated.
Criterion 3—The Proposed Change Does Not
Involve a Significant Reduction in the Margin
of Safety
The proposed change allows, for some
systems, entry into hot shutdown rather than
cold shutdown to repair equipment, if risk is
assessed and managed. The BWROG’s risk
assessment approach is comprehensive and
follows [NRC] staff guidance as documented
in RGs [Regulatory Guides] 1.174 and 1.177.
In addition, the analyses show that the
criteria of the three-tiered approach for
allowing TS changes are met. The risk impact
of the proposed TS changes was assessed
following the three-tiered approach
recommended in RG 1.177. A risk assessment
was performed to justify the proposed TS
changes. The net change to the margin of
safety is insignificant. Therefore, this change
does not involve a significant reduction in a
margin of safety.
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The NRC staff has reviewed the
analysis adopted by the licensee and
based on this review, it appears that the
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 J.
Fewell, Associate General Counsel,
Exelon Generation Company, LLC, 4300
Winfield Road, Warrenville, IL 60555.
NRC Branch Chief: Russell Gibbs.
Nebraska Public Power District, Docket
No. 50–298, Cooper Nuclear Station,
Nemaha County, Nebraska
Date of amendment request: January
14, 2008.
Description of amendment request:
The proposed amendment would revise
the Technical Specification (TS)
requirements related to control room
envelope habitability in accordance
with TS Task Force (TSTF) traveler
TSTF–448–A, ‘‘Control Room
Habitability,’’ 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’’ in the
Federal Register on January 17, 2007
(72 FR 2022). The notice referenced a
model safety evaluation, a model no
significant hazards consideration
(NSHC) determination, and a model
license amendment request published in
the Federal Register on October 17,
2006 (71 FR 61075). In its application
dated January 14, 2008, the licensee
affirmed the applicability of the model
NSHC determination which is presented
below.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), an
analysis of the issue of NSHC adopted
by the licensee 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
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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 upon this review, it appears that
the standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
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proposes to determine that the request
for amendment involves NSHC.
Attorney for licensee: Mr. John C.
McClure, Nebraska Public Power
District, Post Office Box 499, Columbus,
NE 68602–0499.
NRC Branch Chief: Thomas G. Hiltz.
Pacific Gas and Electric Co., Docket No.
50–133, Humboldt Bay Power Plant
(HBPP), Unit 3 Humboldt County,
California
Date of amendment request:
November 5, 2007.
Description of amendment request:
The licensee has proposed an
amendment to Facility Operating
License No. DPR–7 for HBPP Unit 3 to
delete the paragraph 2.C.1 requirement
to implement and maintain a physical
security plan. In conjunction with this
request the licensee is also requesting
exemptions from the requirements in 10
CFR 50.54(p) ‘‘Conditions of Licenses’’
and 10 CFR 73 ‘‘Physical Protection of
Plants and Materials.’’ In addition, the
licensee is requesting rescission of NRC
Order EA–02–077, ‘‘Order for Interim
Safeguards and Security Compensatory
Measures’’ and NRC Order EA–03–099,
‘‘Order for the Implementation of
Additional Security Measures
Associated with Access Authorization,
Fitness for Duty and Behavior
Observation.’’
The requested license amendment,
exemption and rescission would
eliminate the security, fitness for duty
and access authorization requirements
for HBPP Unit 3 after spent nuclear fuel
assemblies and fuel fragment containers
have been transferred from the Spent
Fuel Pool (SFP) to the Humboldt Bay
(HB) Independent Spent Fuel Storage
Installation (ISFSI).
The licensee will be required to
provide protection for the spent fuel in
the HB ISFSI in accordance with the HB
ISFSI physical security plan approved
by NRC License SNM–2514, dated
November 17, 2005, to meet the
requirements of 10 CFR 72, subpart H,
‘‘Physical Protection.’’
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 structures, systems, and components
of the Humboldt Bay Power Plant (HBPP)
Unit 3 and the operating procedures for their
use are unaffected by the proposed change.
The elimination of the security requirements
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for HBPP Unit 3 does not affect possible
initiating events for accidents previously
evaluated or alter the configuration or
operation of the facility.
The accidents previously evaluated
include spent fuel handling accident, Spent
Fuel Pool (SFP) rupture, heavy load drop
onto fuel in the SFP, uncontrolled release of
radioactive liquid radioactive waste,
explosions, release of toxic chemicals and
fire. None of these accidents are impacted by
the elimination of security requirements.
(2) Does the change create the possibility
of a new or different kind of accident from
any accident evaluated?
Response: No.
The proposed change is security related
and has no direct impact on plant equipment
or the procedures for operating plant
equipment. The safety analysis for the facility
remains complete and accurate. There are no
physical changes to the facility, and the plant
conditions for which the design basis
accidents have been evaluated are still valid.
(3) Does the change involve a significant
reduction in a margin of safety?
Response: No.
The proposed change is security related
and has no direct impact on plant equipment
or the procedures for operating plant
equipment. There are no changes to the
design or operation of the facility.
The assumptions for a fuel handling and
other accidents are not affected by the
proposed license amendment. Accordingly,
neither the design basis nor the accident
assumptions in the Defueled Safety Analysis
Report nor the Technical Specifications
Bases are affected. 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: Ms. Jennifer K.
Post, Pacific Gas and Electric Company,
77 Beale Street, B30A, San Francisco,
CA.
NRC Branch Chief: Andrew Persinko.
South Carolina Electric & Gas Company,
South Carolina Public Service
Authority, Docket No. 50–395, Virgil C.
Summer Nuclear Station, Unit No. 1,
Fairfield County, South Carolina Date of
Amendment Request: January 17, 2008.
Description of amendment request:
The proposed amendments would
revise Technical Specification (TS)
3.7.6, ‘‘Control Room Normal and
Emergency Air Handling System,’’ and
TS Section 6.8, ‘‘Procedures and
Programs.’’ These changes are based on
TS Task Force (TSTF) change traveler
TSTF–448, Revision 3 that has been
approved generically for the Standard
Technical Specifications—
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Westinghouse Plants, NUREG–1431.
The NRC staff issued a notice of
availability of a model safety evaluation
and model no significant hazards
consideration (NSHC) determination for
referencing in license amendment
applications in the Federal Register on
January 17, 2007 (72 FR 2022). The
licensee affirmed the applicability of the
model NSHC determination in its
application dated January 17, 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 [control room envelope] 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
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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.
Based upon the reasoning presented above
and the previous discussion of the
amendment request, the requested change
does not involve a no significant hazards
consideration.
The NRC staff proposes to determine
that the amendment request involves no
significant hazards consideration.
Attorney for Licensee: Thomas G.
Eppink, South Carolina Electric & Gas
Company, Post Office Box 764,
Columbia, South Carolina 29218.
NRC Branch Chief: Melanie Wong,
Acting Chief.
STP Nuclear Operating Company,
Docket Nos. 50–498 and 50–499, South
Texas Project, Units 1 and 2, Matagorda
County, Texas
Date of amendment request:
November 8, 2007.
Description of amendment request:
The proposed amendments would
revise Technical Specification 3/4.8.2,
‘‘DC Sources,’’ to modify battery
surveillance requirements. Specifically,
the proposed changes would allow
battery performance discharge testing to
be performed while the associated unit
is at power.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the
issue of no significant hazards
consideration, which is presented
below:
• The proposed change[s] [do] not involve
a significant increase in the probability or
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consequences of an accident previously
evaluated.
Performance of the surveillance is not an
accident initiator. Consequently, the
probability of an accident occurring is not
affected by [these] proposed change[s].
Accident mitigation will be provided by the
redundant channels should an accident occur
while a channel is being tested.
The risk-informed configuration
management program, as approved in
Amendments 179 and 166, effectively
manages the availability of required systems,
structures, and components to assure there is
no significant increase in the probability of
an accident. Therefore, the proposed
change[s] [do] not involve a significant
increase in the probability or consequences
of an accident previously evaluated.
• The proposed change[s] [do] not create
the possibility of a new or different kind of
accident from any previously evaluated.
The proposed change[s] [do] not involve a
new mode of operation or design
configuration. The only change is in the
duration of a battery’s unavailability, which
is established consistent with the level of
associated risk. Therefore, the proposed
change[s] [do] not create the possibility of a
new or different accident from any accident
previously evaluated.
• The proposed change[s] [do] not involve
a significant reduction in the margin of
safety.
The risk-informed configuration
management program assures that adequate
margins of safety are maintained. The
configuration management program
considers cumulative effects of multiple
systems and components being out of service.
Therefore, the proposed change[s] [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 standards of
10 CFR 50.92(c) are satisfied. Therefore,
the NRC staff proposes to determine that
the request for amendments involves no
significant hazards consideration.
Attorney for licensee: A.H. Gutterman,
Esq., Morgan, Lewis & Bockius, 1111
Pennsylvania Avenue, NW.,
Washington, DC 20004.
NRC Branch Chief: Thomas G. Hiltz.
Wolf Creek Nuclear Operating
Corporation, Docket No. 50–482, Wolf
Creek Generating Station, Coffey
County, Kansas
Date of amendment request: January
15, 2008.
Description of amendment request:
The proposed amendment would
modify the Technical Specification (TS)
to establish more effective and
appropriate action, surveillance, and
administrative requirements related to
ensuring the habitability of the control
room envelope (CRE) in accordance
with Nuclear Regulatory Commission
(NRC)–approved TS Task Force (TSTF)
Standard Technical Specification
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change traveler TSTF–448, Revision 3,
‘‘Control Room Habitability.’’
Specifically, the proposed amendment
would modify TS 3.7.10, ‘‘Control Room
Emergency Ventilation System
(CREVS),’’ and would establish a CRE
habitability (CREH) program in TS
Section 5.5, ‘‘Administrative Controls—
Programs and Manuals.’’ 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 January 15, 2008, the licensee
affirmed the applicability of the model
NSHC determination which is presented
below.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), an
analysis of the issue of NSHC adopted
by the licensee 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
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
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Jkt 214001
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
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the request
for amendments involves NSHC.
Attorney for licensee: Terence A.
Burke, Associate General Council—
Nuclear Entergy Services, Inc., 1340
Echelon Parkway, Jackson, Mississippi
39213.
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
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8073
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.
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:
December 21, 2006.
Brief Description of amendments: The
amendments change the Technical
Specifications (TSs) related to the
reactor recirculation system flow
balance.
Date of issuance: December 17, 2007.
Effective date: Date of issuance, to be
implemented within 60 days.
Amendment Nos.: 244 and 272.
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Facility Operating License Nos. DPR–
71 and DPR–62: Amendments changed
the TSs.
Date of initial notice in Federal
Register: March 13, 2007 (72 FR
11385).
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated December 17,
2007.
No significant hazards consideration
comments received: No.
Dominion Nuclear Connecticut, Inc.,
Docket No. 50–336, Millstone Power
Station, Unit No. 2 New London County,
Connecticut
Date of amendment request:
November 8, 2006, as supplemented by
letters dated May 4, October 4, and
November 27, 2007.
Brief description of amendment: The
amendment revises the Millstone Power
Station, Unit No. 2 Technical
Specifications (TSs) Action and
Surveillance Requirements for
instrumentation identified in TSs 3.3.1
and 3.3.2. In particular, the amendment
adds actions to address the inoperability
of one or more automatic bypass
removal channels; revises the
terminology used in the notation of TS
2.2–1 and 3.3–1 relative to the
implementation and automatic removal
of certain Reactor Protective System trip
bypasses; revises the frequency for
performing surveillance of the
automatic bypass removal function
logic; and incorporates two
administrative changes.
Date of issuance: January 29, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 90 days from the date of
issuance.
Amendment No.: 301.
Facility Operating License No. DPR–
65: Amendment revised the License and
Technical Specifications.
Date of initial notice in Federal
Register: April 24, 2007 (72 FR 20380).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated January 29,
2008.
No significant hazards consideration
comments received: No.
mstockstill on PROD1PC66 with NOTICES
Indiana Michigan Power Company,
Docket Nos. 50–315, Donald C. Cook
Nuclear Plant, Units 1 and 2 (DCCNP–
1 and DCCNP–2), Berrien County,
Michigan
Date of application for amendments:
May 11, 2007.
Brief description of amendments: The
amendments revise the DCCNP–1 and
DCCNP–2 Technical Specifications to
increase the power level at which
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Jkt 214001
performance of the trip actuating device
operational test (TADOT) of a reactor
trip following a turbine trip signal is
required. Specifically, the previous
Surveillance Requirement 3.3.1.18
required performance of a TADOT of a
reactor trip on turbine trip prior to
exceeding the P–7 interlock (at
approximately 10 percent of the rated
thermal power (RTP)) whenever the unit
has been in Mode 3, if not performed
within the previous 31 days. The
amendments replace the ‘‘P–7’’
interlock with the ‘‘P–8’’ interlock (at
approximately 31 percent RTP).
Date of issuance: January 11, 2008.
Effective date: As of the date of
issuance, and shall be implemented
within 45 days.
Amendment No.: 301 (for DCCNP–1)
and 284 (for DCCNP–2).
Facility Operating License Nos. DPR–
58 and DPR–74: Amendments revise the
Renewed Operating Licenses and
Technical Specifications.
Date of initial notice in Federal
Register: June 19, 2007 (72 FR 33783).
The Commission’s related evaluation
of the amendment is contained in a
safety evaluation dated January 11,
2008.
No significant hazards consideration
comments received: No.
Luminant Generation Company LLC,
Docket Nos. 50–445 and 50–446,
Comanche Peak Steam Electric Station,
Unit Nos. 1 and 2, Somervell County,
Texas
Date of amendment request:
December 19, 2006, as supplemented by
letters dated November 30, and
December 6, 2007.
Brief description of amendments: The
amendments revise Technical
Specifications (TS) 3.7.5, ‘‘Auxiliary
Feedwater (AFW) System,’’ TS 3.8.1,
‘‘AC [Alternating Current] Sources—
Operating,’’ TS 3.8.9, ‘‘Distribution
Systems—Operating,’’ and TS Example
1.3–3.
Date of issuance: January 25, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 120 days from the date of
issuance.
Amendment Nos.: Unit 1—142; Unit
2—142.
Facility Operating License Nos. NPF–
87 and NPF–89: The amendments
revised the Facility Operating Licenses
and Technical Specifications.
Date of initial notice in Federal
Register: April 10, 2007 (72 FR 17952).
The supplemental letters dated
November 30, and December 6, 2007,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
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noticed, and did not change the staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register on
April 10, 2007 (72 FR 17952). The
Commission’s related evaluation of the
amendments is contained in a Safety
Evaluation dated January 25, 2008.
No significant hazards consideration
comments received: No.
Nuclear Management Company, LLC,
Docket No. 50–263, Monticello Nuclear
Generating Plant, Wright County,
Minnesota
Date of application for amendment:
September 17, 2007.
Brief description of amendment: The
amendment revised Technical
Specifications Section 3.7.5 to specify
the conditions and required actions
associated with two control room
ventilation subsystems inoperable. The
revised Section 3.7.5 follows Technical
Specifications Task Force (TSTF)
Change Traveler TSTF–477, Revision 3,
‘‘Add Action for Two Inoperable
Control Room AC Subsystems.’’
Date of issuance: January 23, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 90 days.
Amendment No.: 154.
Facility Operating License No. DPR–
22. Amendment revised the Facility
Operating License and Technical
Specifications.
Date of initial notice in Federal
Register: November 6, 2007 (72 FR
62689).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated January 23,
2008.
No significant hazards consideration
comments received: No.
Nuclear Management Company, LLC,
Docket Nos. 50–282 and 50–306, Prairie
Island Nuclear Generating Plant, Units
1 and 2, Goodhue County, Minnesota
Date of application for amendments:
January 29, 2007, supplemented by
letters dated November 19, 2007, and
December 13, 2007.
Brief description of amendments: The
amendments revised the Technical
Specification (TS) 3.5.3 ‘‘ECCSShutdown’’ for Prairie Island Nuclear
Generating Plant (PINGP), Units 1 and 2
to change operability requirements for
the safety injection (SI) subsystem by
addition of a Note to the Limiting
Condition for Operation 3.5.3 ‘‘One
ECCS train shall be OPERABLE.’’ The
Note states ‘‘An SI train may be
considered OPERABLE when the pump
is capable of being manually started
from the control room.’’
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Date of issuance: January 28, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 90 days.
Amendment Nos.: 183, 173.
Facility Operating License Nos. DPR–
42 and DPR–60: Amendments revised
the Technical Specifications.
Date of initial notice in Federal
Register: March 13, 2007 (72 FR 11392).
The supplemental letters contained
clarifying information and did not
change the initial no significant hazards
consideration determination, and did
not expand the scope of the original
Federal Register notice. The
Commission’s related evaluation of the
amendments is contained in a Safety
Evaluation dated January 28, 2008.
No significant hazards consideration
comments received. No.
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PSEG Nuclear LLC, Docket No. 50–354,
Hope Creek Generating Station, Salem
County, New Jersey
Date of application for amendment:
April 17, 2007, as supplemented by
letter dated June 29, 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: January 24, 2008.
Effective date: As of the date of
issuance, to be implemented within 180
days.
Amendment No.: 173.
Facility Operating License No. NPF–
57: The amendment revised the
Technical Specifications and the
License.
Date of initial notice in Federal
Register: June 5, 2007 (72 FR 31103).
The letter dated June 29, 2007,
provided clarifying information that did
not change the initial proposed no
significant hazards consideration
determination or expand the application
beyond the scope of the original Federal
Register notice.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated January 24,
2008.
No significant hazards consideration
comments received: No.
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PSEG Nuclear LLC, Docket Nos. 50–272
and 50–311, Salem Nuclear Generating
Station, Unit Nos. 1 and 2, Salem
County, New Jersey
Date of application for amendments:
April 15, 2007, as supplemented on
December 10, 2007.
Brief description of amendments: The
amendments establish 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: January 24, 2008.
Effective date: As of the date of
issuance, to be implemented within 180
days.
Amendment Nos.: 286 and 269.
Facility Operating License Nos. DPR–
70 and DPR–75: The amendments
revised the Technical Specifications and
the License.
Date of initial notice in Federal
Register: June 5, 2007 (72 FR 31104).
The letter dated December 10, 2007,
provided clarifying information that did
not change the initial proposed no
significant hazards consideration
determination or expand the application
beyond the scope of the original Federal
Register notice.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated January 24,
2008.
No significant hazards consideration
comments received: No
Tennessee Valley Authority, Docket No.
50–390, Watts Bar Nuclear Plant, Unit 1,
Rhea County, Tennessee
Date of application for amendment:
April 25, 2007, as supplemented August
22, 2007.
Brief description of amendment: The
amendment revises Technical
Specification Surveillance
Requirements 3.5.1.4, ‘‘Accumulators,’’
and 3.5.4.3, ‘‘Refueling Water Storage
Tanks,’’ to remove the note limiting the
number of tritium producing burnable
absorber rods (TPBARs) to no more than
240, and revises TS 4.2.1, ‘‘Fuel
Assemblies,’’ to revise the maximum
number of TPBARs that can be
irradiated in the Watts Bar Unit 1
reactor core to 400.
Date of issuance: January 18, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 45 days of issuance.
Amendment No.: 67.
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Facility Operating License No. NPF–
90: Amendment revises the Technical
Specifications.
Date of initial notice in Federal
Register: June 5, 2007 (72 FR 31105).
The supplemental letter dated August
22, 2007, provided clarifying
information that was within the scope of
the initial notice 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 January 18,
2008.
No significant hazards consideration
comments received: No.
Virginia Electric and Power Company, et
al., Docket Nos. 50–280 and 50–281,
Surry Power Station, Unit Nos. 1 and 2,
Surry County, Virginia
Date of application for amendments:
February 26, 2007, as supplemented on
April 5, May 31, July 13, July 20,
September 25, and November 28, 2007,
and January 14, 2008.
Brief description of amendments:
These amendments added an operating
license condition and revised the
technical specifications to permit the
replacement of main control room
(MCR) and emergency switchgear room
(ESGR) air-conditioning system (ACS)
chilled water piping by using temporary
45-day and 14-day allowed outage times
(AOTs) four times in a 24-month span.
Date of issuance: January 23, 2008.
Effective date: As of the date of
issuance and shall be implemented
within 30 days.
Amendment Nos.: 258, 257.
Renewed Facility Operating License
Nos. DPR–32 and DPR–37: Amendments
changed the licenses and the technical
specifications.
Date of initial notice in Federal
Register: March 27, 2007 (72 FR 14308).
The supplements dated April 5, May
31, July 13, July 20, September 25, and
November 28, 2007, and January 14,
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. The Commission’s
related evaluation of the amendments is
contained in a Safety Evaluation dated
January 23, 2008.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 31st day
of January 2008.
E:\FR\FM\12FEN1.SGM
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8076
Federal Register / Vol. 73, No. 29 / Tuesday, February 12, 2008 / Notices
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E8–2143 Filed 2–11–08; 8:45 am]
Week of March 10, 2008—Tentative
There are no meetings scheduled for
the Week of March 10, 2008.
Week of March 17, 2008—Tentative
Matters To Be Considered
9:30 a.m. Briefing by Independent
External Panel to Identify
Vulnerabilities in the U.S. NRC’s
Materials Licensing Program (Public
Meeting) (Contact: Aaron T.
McCraw, 301–415–1277)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
*
*
*
*
*
* The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—(301) 415–1292.
Contact person for more information:
Michelle Schroll, (301) 415–1662.
*
*
*
*
*
Week of February 11, 2008
Additional Information
Monday, February 11, 2008
Affirmation of ‘‘Final Rule—10 CFR
Part 73 ‘Safeguards Information
Protection Requirements’ (RIN 3150–
AH57)’’ tentatively scheduled on
February 11, 2008, at 12:55 p.m. has
been tentatively rescheduled on
Wednesday, February 20, 2008, at 1:25
p.m.
*
*
*
*
*
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/about-nrc/policymaking/schedule.html.
*
*
*
*
*
The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify the
NRC’s Disability Program Coordinator,
Rohn Brown, at 301–492–2279, TDD:
301–415–2100, or by e-mail at
REB3@nrc.gov. Determinations on
requests for reasonable accommodation
will be made on a case-by-case basis.
*
*
*
*
*
This notice is distributed by mail to
several hundred subscribers; if you no
longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301–415–1969).
In addition, distribution of this meeting
notice over the Internet system is
available. If you are interested in
receiving this Commission meeting
schedule electronically, please send an
electronic message to dkw@nrc.gov.
NUCLEAR REGULATORY
COMMISSION
Sunshine Act Meeting Notice
AGENCY HOLDING THE MEETINGS: Nuclear
Regulatory Commission.
DATES: Weeks of February 11, 18, 25,
March 3, 10, 17, 2008.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
1 p.m. Discussion of Security Issues
(Closed—Ex. 1)
Week of February 18, 2008—Tentative
Tuesday, February 19, 2008
10:30 a.m. Meeting with the National
Academies Radiation Source Use
and Replacement Study Committee
(Closed—Ex. 1)
Wednesday, February 20, 2008
9:30 a.m. Periodic Meeting on New
Reactor Issues, Part 1 (Public
Meeting) (Contact: Donna Williams,
301–415–1322)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
1:25 p.m. Affirmation Session (Public
Meeting) (Tentative)
a. Final Rule—10 CFR Part 73
‘‘Safeguards Information Protection
Requirements’’ (RIN 3150—AH57)
(Tentative)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
1:30 p.m. Periodic Meeting on New
Reactor Issues, Part 2 (Public
Meeting) (Contact: Donna Williams,
301–415–1322)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
mstockstill on PROD1PC66 with NOTICES
Week of February 25, 2008—Tentative
There are no meetings scheduled for
the Week of February 25, 2008.
Week of March 3, 2008—Tentative
There are no meetings scheduled for
the Week of March 3, 2008.
17:46 Feb 11, 2008
Jkt 214001
BILLING CODE 7590–01–P
Tuesday, March 18, 2008
BILLING CODE 7590–01–P
VerDate Aug<31>2005
Dated: February 7, 2008.
R. Michelle Schroll,
Office of the Secretary.
[FR Doc. 08–657 Filed 2–8–08; 1:43 pm]
PO 00000
Frm 00047
Fmt 4703
Sfmt 4703
POSTAL SERVICE
Notice of Intent To Prepare an
Environmental Impact Statement for
the Proposed Construction and
Operation of a Mail Processing Facility
in Aliso Viejo, CA
Postal Service.
Notice.
AGENCY:
ACTION:
SUMMARY: To comply with the
requirements of the National
Environmental Policy Act (NEPA), the
Postal Service intends to prepare an
Environmental Impact Statement (EIS)
for the proposed construction and
operation of a mail processing facility in
Aliso Viejo, Orange County, California.
The public is invited to participate in
the project scoping process, to review
and comment on the draft EIS, and to
attend public meetings.
DATES: Please submit written scoping
comments by March 9, 2008. This notice
is the first step in the EIS process. A
separate notice of availability will be
issued when the draft EIS is available
for public review.
To solicit public comments, a public
scoping hearing will be held from 5:30
to 8:30 p.m. on February 27, 2008, at the
Wood Canyon Elementary School,
23431 Knollwood Avenue, Aliso Viejo,
California; (949) 448–0012.
ADDRESSES: To submit comments,
request copies of the draft EIS or final
EIS when available, or for more
information, contact Emmy Andrews,
Pacific Facilities Service Office, United
States Postal Service, 395 Oyster Point
Boulevard, Suite 225, South San
Francisco, CA 94080–0300; (650) 615–
7200.
FOR FURTHER INFORMATION CONTACT:
Emmy Andrews, 650–615–7200.
SUPPLEMENTARY INFORMATION: To comply
with the requirements of the National
Environmental Policy Act (NEPA), the
Postal Service intends to prepare an
environmental impact statement (EIS)
for the proposed construction and
operation of a mail processing facility
on a 25-acre parcel owned by the Postal
Service at 50 Liberty, Aliso Viejo,
Orange County, California. The EIS will
be prepared in accordance with the
National Environmental Policy Act
(NEPA) of 1969, 42 U.S.C. 4321 et seq.,
the Council on Environmental Quality
regulations for implementing NEPA, 40
E:\FR\FM\12FEN1.SGM
12FEN1
Agencies
[Federal Register Volume 73, Number 29 (Tuesday, February 12, 2008)]
[Notices]
[Pages 8068-8076]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-2143]
=======================================================================
-----------------------------------------------------------------------
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 January 17, 2008, to January 30, 2008. The
last biweekly notice was published on (73 FR 5215).
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 6D22, 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 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
[[Page 8069]]
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 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 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 website 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 website 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: 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 email to pdr@nrc.gov.
[[Page 8070]]
AmerGen Energy Company, LLC, Docket No. 50-461, Clinton Power Station,
Unit No.1, DeWitt County, Illinois
Date of amendment request: June 21, 2007.
Description of amendment request: A change is proposed to the
technical specifications (TSs) of Clinton Power Station, Unit No. 1
(CPS), consistent with TS Task Force (TSTF) change TSTF-423 to the
standard technical specifications (STSs) for boiling-water reactor
(BWR) plants to allow, for some systems, entry into hot shutdown rather
than cold shutdown to repair equipment, if risk is assessed and managed
consistent with the program in place for complying with the
requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.65(a)(4). The proposed amendment would modify the TS to
risk-informed requirements regarding selected required action end
states provided in TSTF-423, Revision 0, ``Technical Specification End
States, NEDC-32988-A.''
The CPS has reviewed the proposed no significant hazards
consideration (NSHC) determination published on March 23, 2006, (71 FR
14743) as part of the consolidated line item improvement process and,
based on this review, it appears that the three standards of 10 CFR
50.92(c) are satisfied. The licensee has affirmed the applicability of
the following NSHC determination in its application.
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 allows a change to certain required end
states when the TS Completion Times for remaining in power operation
will be exceeded. Most of the requested technical specification (TS)
changes are to permit an end state of hot shutdown (Mode 3) rather
than an end state of cold shutdown (Mode 4) contained in the current
TS. The request was limited to: (1) Those end states where entry
into the shutdown mode is for a short interval, (2) entry is
initiated by inoperability of a single train of equipment or a
restriction on a plant operational parameter, unless otherwise
stated in the applicable technical specification, and (3) the
primary purpose is to correct the initiating condition and return to
power operation as soon as is practical. Risk insights from both the
qualitative and quantitative risk assessments were used in specific
TS assessments. Such assessments are documented in Section 6 of GE
NEDC-32988, Revision 2, ``Technical Justification to Support Risk
Informed Modification to Selected Required Action End States for BWR
Plants.'' They provide an integrated discussion of deterministic and
probabilistic issues, focusing on specific technical specifications,
which are used to support the proposed TS end state and associated
restrictions. The [NRC] staff finds that the risk insights support
the conclusions of the specific TS assessments. Therefore, the
probability of an accident previously evaluated is not significantly
increased, if at all. The consequences of an accident after adopting
proposed TSTF-423, are no different than the consequences of an
accident prior to adopting TSTF-423. Therefore, the consequences of
an accident previously evaluated are not significantly affected by
this change. The addition of a requirement to assess and manage the
risk introduced by this change will further minimize possible
concerns. Therefore, this 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 Previously Evaluated.
The proposed change does not involve a physical alteration of
the plant (no new or different type of equipment will be installed).
If risk is assessed and managed, allowing a change to certain
required end states when the TS Completion Times for remaining in
power operation are exceeded, i.e., entry into hot shutdown rather
than cold shutdown to repair equipment, will not introduce new
failure modes or effects and will not, in the absence of other
unrelated failures, lead to an accident whose consequences exceed
the consequences of accidents previously evaluated. The addition of
a requirement to assess and manage the risk introduced by this
change and the commitment by the licensee to adhere to the guidance
in TSTF-IG-05-02, Implementation Guidance for TSTF-423, Revision 0,
``Technical Specifications End States, NEDC-32988-A,'' will further
minimize possible concerns. Thus, this change does not create the
possibility of a new or different kind of accident from an accident
previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed change allows, for some systems, entry into hot
shutdown rather than cold shutdown to repair equipment, if risk is
assessed and managed. The BWROG's risk assessment approach is
comprehensive and follows [NRC] staff guidance as documented in RGs
[Regulatory Guides] 1.174 and 1.177. In addition, the analyses show
that the criteria of the three-tiered approach for allowing TS
changes are met. The risk impact of the proposed TS changes was
assessed following the three-tiered approach recommended in RG
1.177. A risk assessment was performed to justify the proposed TS
changes. The net change to the margin of safety is insignificant.
Therefore, this 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 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 J. Fewell, Associate General
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road,
Warrenville, IL 60555.
NRC Branch Chief: Russell Gibbs.
Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear
Station, Nemaha County, Nebraska
Date of amendment request: January 14, 2008.
Description of amendment request: The proposed amendment would
revise the Technical Specification (TS) requirements related to control
room envelope habitability in accordance with TS Task Force (TSTF)
traveler TSTF-448-A, ``Control Room Habitability,'' 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'' in the Federal Register on January 17, 2007 (72 FR 2022). The
notice referenced a model safety evaluation, a model no significant
hazards consideration (NSHC) determination, and a model license
amendment request published in the Federal Register on October 17, 2006
(71 FR 61075). In its application dated January 14, 2008, the licensee
affirmed the applicability of the model NSHC determination which is
presented below.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of NSHC adopted by the licensee 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
[[Page 8071]]
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 upon this review, it appears that the standards of 10 CFR
50.92(c) are satisfied. Therefore, the NRC staff proposes to determine
that the request for amendment involves NSHC.
Attorney for licensee: Mr. John C. McClure, Nebraska Public Power
District, Post Office Box 499, Columbus, NE 68602-0499.
NRC Branch Chief: Thomas G. Hiltz.
Pacific Gas and Electric Co., Docket No. 50-133, Humboldt Bay Power
Plant (HBPP), Unit 3 Humboldt County, California
Date of amendment request: November 5, 2007.
Description of amendment request: The licensee has proposed an
amendment to Facility Operating License No. DPR-7 for HBPP Unit 3 to
delete the paragraph 2.C.1 requirement to implement and maintain a
physical security plan. In conjunction with this request the licensee
is also requesting exemptions from the requirements in 10 CFR 50.54(p)
``Conditions of Licenses'' and 10 CFR 73 ``Physical Protection of
Plants and Materials.'' In addition, the licensee is requesting
rescission of NRC Order EA-02-077, ``Order for Interim Safeguards and
Security Compensatory Measures'' and NRC Order EA-03-099, ``Order for
the Implementation of Additional Security Measures Associated with
Access Authorization, Fitness for Duty and Behavior Observation.''
The requested license amendment, exemption and rescission would
eliminate the security, fitness for duty and access authorization
requirements for HBPP Unit 3 after spent nuclear fuel assemblies and
fuel fragment containers have been transferred from the Spent Fuel Pool
(SFP) to the Humboldt Bay (HB) Independent Spent Fuel Storage
Installation (ISFSI).
The licensee will be required to provide protection for the spent
fuel in the HB ISFSI in accordance with the HB ISFSI physical security
plan approved by NRC License SNM-2514, dated November 17, 2005, to meet
the requirements of 10 CFR 72, subpart H, ``Physical Protection.''
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 structures, systems, and components of the Humboldt Bay
Power Plant (HBPP) Unit 3 and the operating procedures for their use
are unaffected by the proposed change. The elimination of the
security requirements for HBPP Unit 3 does not affect possible
initiating events for accidents previously evaluated or alter the
configuration or operation of the facility.
The accidents previously evaluated include spent fuel handling
accident, Spent Fuel Pool (SFP) rupture, heavy load drop onto fuel
in the SFP, uncontrolled release of radioactive liquid radioactive
waste, explosions, release of toxic chemicals and fire. None of
these accidents are impacted by the elimination of security
requirements.
(2) Does the change create the possibility of a new or different
kind of accident from any accident evaluated?
Response: No.
The proposed change is security related and has no direct impact
on plant equipment or the procedures for operating plant equipment.
The safety analysis for the facility remains complete and accurate.
There are no physical changes to the facility, and the plant
conditions for which the design basis accidents have been evaluated
are still valid.
(3) Does the change involve a significant reduction in a margin
of safety?
Response: No.
The proposed change is security related and has no direct impact
on plant equipment or the procedures for operating plant equipment.
There are no changes to the design or operation of the facility.
The assumptions for a fuel handling and other accidents are not
affected by the proposed license amendment. Accordingly, neither the
design basis nor the accident assumptions in the Defueled Safety
Analysis Report nor the Technical Specifications Bases are affected.
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: Ms. Jennifer K. Post, Pacific Gas and
Electric Company, 77 Beale Street, B30A, San Francisco, CA.
NRC Branch Chief: Andrew Persinko.
South Carolina Electric & Gas Company, South Carolina Public Service
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit
No. 1, Fairfield County, South Carolina Date of Amendment Request:
January 17, 2008.
Description of amendment request: The proposed amendments would
revise Technical Specification (TS) 3.7.6, ``Control Room Normal and
Emergency Air Handling System,'' and TS Section 6.8, ``Procedures and
Programs.'' These changes are based on TS Task Force (TSTF) change
traveler TSTF-448, Revision 3 that has been approved generically for
the Standard Technical Specifications--
[[Page 8072]]
Westinghouse Plants, NUREG-1431. The NRC staff issued a notice of
availability of a model safety evaluation and model no significant
hazards consideration (NSHC) determination for referencing in license
amendment applications in the Federal Register on January 17, 2007 (72
FR 2022). The licensee affirmed the applicability of the model NSHC
determination in its application dated January 17, 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 [control room
envelope] 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.
Based upon the reasoning presented above and the previous
discussion of the amendment request, the requested change does not
involve a no significant hazards consideration.
The NRC staff proposes to determine that the amendment request
involves no significant hazards consideration.
Attorney for Licensee: Thomas G. Eppink, South Carolina Electric &
Gas Company, Post Office Box 764, Columbia, South Carolina 29218.
NRC Branch Chief: Melanie Wong, Acting Chief.
STP Nuclear Operating Company, Docket Nos. 50-498 and 50-499, South
Texas Project, Units 1 and 2, Matagorda County, Texas
Date of amendment request: November 8, 2007.
Description of amendment request: The proposed amendments would
revise Technical Specification 3/4.8.2, ``DC Sources,'' to modify
battery surveillance requirements. Specifically, the proposed changes
would allow battery performance discharge testing to be performed while
the associated unit is at power.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
The proposed change[s] [do] not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
Performance of the surveillance is not an accident initiator.
Consequently, the probability of an accident occurring is not
affected by [these] proposed change[s]. Accident mitigation will be
provided by the redundant channels should an accident occur while a
channel is being tested.
The risk-informed configuration management program, as approved
in Amendments 179 and 166, effectively manages the availability of
required systems, structures, and components to assure there is no
significant increase in the probability of an accident. Therefore,
the proposed change[s] [do] not involve a significant increase in
the probability or consequences of an accident previously evaluated.
The proposed change[s] [do] not create the possibility
of a new or different kind of accident from any previously
evaluated.
The proposed change[s] [do] not involve a new mode of operation
or design configuration. The only change is in the duration of a
battery's unavailability, which is established consistent with the
level of associated risk. Therefore, the proposed change[s] [do] not
create the possibility of a new or different accident from any
accident previously evaluated.
The proposed change[s] [do] not involve a significant
reduction in the margin of safety.
The risk-informed configuration management program assures that
adequate margins of safety are maintained. The configuration
management program considers cumulative effects of multiple systems
and components being out of service. Therefore, the proposed
change[s] [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 standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
request for amendments involves no significant hazards consideration.
Attorney for licensee: A.H. Gutterman, Esq., Morgan, Lewis &
Bockius, 1111 Pennsylvania Avenue, NW., Washington, DC 20004.
NRC Branch Chief: Thomas G. Hiltz.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek
Generating Station, Coffey County, Kansas
Date of amendment request: January 15, 2008.
Description of amendment request: The proposed amendment would
modify the Technical Specification (TS) to establish more effective and
appropriate action, surveillance, and administrative requirements
related to ensuring the habitability of the control room envelope (CRE)
in accordance with Nuclear Regulatory Commission (NRC)-approved TS Task
Force (TSTF) Standard Technical Specification
[[Page 8073]]
change traveler TSTF-448, Revision 3, ``Control Room Habitability.''
Specifically, the proposed amendment would modify TS 3.7.10, ``Control
Room Emergency Ventilation System (CREVS),'' and would establish a CRE
habitability (CREH) program in TS Section 5.5, ``Administrative
Controls--Programs and Manuals.'' 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 January 15, 2008, the
licensee affirmed the applicability of the model NSHC determination
which is presented below.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of NSHC adopted by the licensee 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
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 standards of 10 CFR
50.92(c) are satisfied. Therefore, the NRC staff proposes to determine
that the request for amendments involves NSHC.
Attorney for licensee: Terence A. Burke, Associate General
Council--Nuclear Entergy Services, Inc., 1340 Echelon Parkway, Jackson,
Mississippi 39213.
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.
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: December 21, 2006.
Brief Description of amendments: The amendments change the
Technical Specifications (TSs) related to the reactor recirculation
system flow balance.
Date of issuance: December 17, 2007.
Effective date: Date of issuance, to be implemented within 60 days.
Amendment Nos.: 244 and 272.
[[Page 8074]]
Facility Operating License Nos. DPR-71 and DPR-62: Amendments
changed the TSs.
Date of initial notice in Federal Register: March 13, 2007 (72 FR
11385).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated December 17, 2007.
No significant hazards consideration comments received: No.
Dominion Nuclear Connecticut, Inc., Docket No. 50-336, Millstone Power
Station, Unit No. 2 New London County, Connecticut
Date of amendment request: November 8, 2006, as supplemented by
letters dated May 4, October 4, and November 27, 2007.
Brief description of amendment: The amendment revises the Millstone
Power Station, Unit No. 2 Technical Specifications (TSs) Action and
Surveillance Requirements for instrumentation identified in TSs 3.3.1
and 3.3.2. In particular, the amendment adds actions to address the
inoperability of one or more automatic bypass removal channels; revises
the terminology used in the notation of TS 2.2-1 and 3.3-1 relative to
the implementation and automatic removal of certain Reactor Protective
System trip bypasses; revises the frequency for performing surveillance
of the automatic bypass removal function logic; and incorporates two
administrative changes.
Date of issuance: January 29, 2008.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: 301.
Facility Operating License No. DPR-65: Amendment revised the
License and Technical Specifications.
Date of initial notice in Federal Register: April 24, 2007 (72 FR
20380).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 29, 2008.
No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315, Donald C. Cook
Nuclear Plant, Units 1 and 2 (DCCNP-1 and DCCNP-2), Berrien County,
Michigan
Date of application for amendments: May 11, 2007.
Brief description of amendments: The amendments revise the DCCNP-1
and DCCNP-2 Technical Specifications to increase the power level at
which performance of the trip actuating device operational test (TADOT)
of a reactor trip following a turbine trip signal is required.
Specifically, the previous Surveillance Requirement 3.3.1.18 required
performance of a TADOT of a reactor trip on turbine trip prior to
exceeding the P-7 interlock (at approximately 10 percent of the rated
thermal power (RTP)) whenever the unit has been in Mode 3, if not
performed within the previous 31 days. The amendments replace the ``P-
7'' interlock with the ``P-8'' interlock (at approximately 31 percent
RTP).
Date of issuance: January 11, 2008.
Effective date: As of the date of issuance, and shall be
implemented within 45 days.
Amendment No.: 301 (for DCCNP-1) and 284 (for DCCNP-2).
Facility Operating License Nos. DPR-58 and DPR-74: Amendments
revise the Renewed Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: June 19, 2007 (72 FR
33783).
The Commission's related evaluation of the amendment is contained
in a safety evaluation dated January 11, 2008.
No significant hazards consideration comments received: No.
Luminant Generation Company LLC, Docket Nos. 50-445 and 50-446,
Comanche Peak Steam Electric Station, Unit Nos. 1 and 2, Somervell
County, Texas
Date of amendment request: December 19, 2006, as supplemented by
letters dated November 30, and December 6, 2007.
Brief description of amendments: The amendments revise Technical
Specifications (TS) 3.7.5, ``Auxiliary Feedwater (AFW) System,'' TS
3.8.1, ``AC [Alternating Current] Sources--Operating,'' TS 3.8.9,
``Distribution Systems--Operating,'' and TS Example 1.3-3.
Date of issuance: January 25, 2008.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment Nos.: Unit 1--142; Unit 2--142.
Facility Operating License Nos. NPF-87 and NPF-89: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: April 10, 2007 (72 FR
17952). The supplemental letters dated November 30, and December 6,
2007, provided additional information that clarified the application,
did not expand the scope of the application as originally noticed, and
did not change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register on
April 10, 2007 (72 FR 17952). The Commission's related evaluation of
the amendments is contained in a Safety Evaluation dated January 25,
2008.
No significant hazards consideration comments received: No.
Nuclear Management Company, LLC, Docket No. 50-263, Monticello Nuclear
Generating Plant, Wright County, Minnesota
Date of application for amendment: September 17, 2007.
Brief description of amendment: The amendment revised Technical
Specifications Section 3.7.5 to specify the conditions and required
actions associated with two control room ventilation subsystems
inoperable. The revised Section 3.7.5 follows Technical Specifications
Task Force (TSTF) Change Traveler TSTF-477, Revision 3, ``Add Action
for Two Inoperable Control Room AC Subsystems.''
Date of issuance: January 23, 2008.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment No.: 154.
Facility Operating License No. DPR-22. Amendment revised the
Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: November 6, 2007 (72 FR
62689).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 23, 2008.
No significant hazards consideration comments received: No.
Nuclear Management Company, LLC, Docket Nos. 50-282 and 50-306, Prairie
Island Nuclear Generating Plant, Units 1 and 2, Goodhue County,
Minnesota
Date of application for amendments: January 29, 2007, supplemented
by letters dated November 19, 2007, and December 13, 2007.
Brief description of amendments: The amendments revised the
Technical Specification (TS) 3.5.3 ``ECCS-Shutdown'' for Prairie Island
Nuclear Generating Plant (PINGP), Units 1 and 2 to change operability
requirements for the safety injection (SI) subsystem by addition of a
Note to the Limiting Condition for Operation 3.5.3 ``One ECCS train
shall be OPERABLE.'' The Note states ``An SI train may be considered
OPERABLE when the pump is capable of being manually started from the
control room.''
[[Page 8075]]
Date of issuance: January 28, 2008.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment Nos.: 183, 173.
Facility Operating License Nos. DPR-42 and DPR-60: Amendments
revised the Technical Specifications.
Date of initial notice in Federal Register: March 13, 2007 (72 FR
11392).
The supplemental letters contained clarifying information and did
not change the initial no significant hazards consideration
determination, and did not expand the scope of the original Federal
Register notice. The Commission's related evaluation of the amendments
is contained in a Safety Evaluation dated January 28, 2008.
No significant hazards consideration comments received. No.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station,
Salem County, New Jersey
Date of application for amendment: April 17, 2007, as supplemented
by letter dated June 29, 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: January 24, 2008.
Effective date: As of the date of issuance, to be implemented
within 180 days.
Amendment No.: 173.
Facility Operating License No. NPF-57: The amendment revised the
Technical Specifications and the License.
Date of initial notice in Federal Register: June 5, 2007 (72 FR
31103).
The letter dated June 29, 2007, provided clarifying information
that did not change the initial proposed no significant hazards
consideration determination or expand the application beyond the scope
of the original Federal Register notice.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 24, 2008.
No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear
Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey
Date of application for amendments: April 15, 2007, as supplemented
on December 10, 2007.
Brief description of amendments: The amendments establish 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: January 24, 2008.
Effective date: As of the date of issuance, to be implemented
within 180 days.
Amendment Nos.: 286 and 269.
Facility Operating License Nos. DPR-70 and DPR-75: The amendments
revised the Technical Specifications and the License.
Date of initial notice in Federal Register: June 5, 2007 (72 FR
31104).
The letter dated December 10, 2007, provided clarifying information
that did not change the initial proposed no significant hazards
consideration determination or expand the application beyond the scope
of the original Federal Register notice.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 24, 2008.
No significant hazards consideration comments received: No
Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant,
Unit 1, Rhea County, Tennessee
Date of application for amendment: April 25, 2007, as supplemented
August 22, 2007.
Brief description of amendment: The amendment revises Technical
Specification Surveillance Requirements 3.5.1.4, ``Accumulators,'' and
3.5.4.3, ``Refueling Water Storage Tanks,'' to remove the note limiting
the number of tritium producing burnable absorber rods (TPBARs) to no
more than 240, and revises TS 4.2.1, ``Fuel Assemblies,'' to revise the
maximum number of TPBARs that can be irradiated in the Watts Bar Unit 1
reactor core to 400.
Date of issuance: January 18, 2008.
Effective date: As of the date of issuance and shall be implemented
within 45 days of issuance.
Amendment No.: 67.
Facility Operating License No. NPF-90: Amendment revises the
Technical Specifications.
Date of initial notice in Federal Register: June 5, 2007 (72 FR
31105). The supplemental letter dated August 22, 2007, provided
clarifying information that was within the scope of the initial notice
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 January 18, 2008.
No significant hazards consideration comments received: No.
Virginia Electric and Power Company, et al., Docket Nos. 50-280 and 50-
281, Surry Power Station, Unit Nos. 1 and 2, Surry County, Virginia
Date of application for amendments: February 26, 2007, as
supplemented on April 5, May 31, July 13, July 20, September 25, and
November 28, 2007, and January 14, 2008.
Brief description of amendments: These amendments added an
operating license condition and revised the technical specifications to
permit the replacement of main control room (MCR) and emergency
switchgear room (ESGR) air-conditioning system (ACS) chilled water
piping by using temporary 45-day and 14-day allowed outage times (AOTs)
four times in a 24-month span.
Date of issuance: January 23, 2008.
Effective date: As of the date of issuance and shall be implemented
within 30 days.
Amendment Nos.: 258, 257.
Renewed Facility Operating License Nos. DPR-32 and DPR-37:
Amendments changed the licenses and the technical specifications.
Date of initial notice in Federal Register: March 27, 2007 (72 FR
14308).
The supplements dated April 5, May 31, July 13, July 20, September
25, and November 28, 2007, and January 14, 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.
The Commission's related evaluation of the amendments is contained in a
Safety Evaluation dated January 23, 2008.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 31st day of January 2008.
[[Page 8076]]
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E8-2143 Filed 2-11-08; 8:45 am]
BILLING CODE 7590-01-P