FirstEnergy Nuclear Operating Company, Firstenergy Nuclear Generation Corp.; Ohio Edison Company; The Toledo Edison Company; Beaver Valley Power Station, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact, 6611-6612 [E7-2373]
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Federal Register / Vol. 72, No. 28 / Monday, February 12, 2007 / Notices
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
requestors/petitioner’s interest. The
petition must also identify 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 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 intends to rely to establish
those facts or expert opinion. The
petition must include sufficient
information to show that a genuine
dispute exists with the applicant on a
material issue of law or fact.
Contentions shall be limited to matters
within the scope of the amendment
under consideration. The contention
must be one which, if proven, would
entitle the petitioner 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, 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.
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19:52 Feb 09, 2007
Jkt 211001
Nontimely requests and/or petitions
and contentions will not be entertained
absent a determination by the
Commission or the presiding officer of
the Atomic Safety and Licensing Board
that the petition, request and/or the
contentions should be granted based on
a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)–(viii).
A request for a hearing or a petition
for leave to intervene must be filed 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; (2) courier, express
mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland, 20852,
Attention: Rulemaking and
Adjudications Staff; (3) E-mail
addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission,
HEARINGDOCKET@NRC.GOV; or (4)
facsimile transmission addressed to the
Office of the Secretary, U.S. Nuclear
Regulatory Commission, Washington,
DC, Attention: Rulemakings and
Adjudications Staff at (301) 415–1101,
verification number is (301) 415–1966.
A copy of the request for hearing and
petition for leave to intervene should
also be sent to the Office of the General
Counsel, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, and it is requested that copies be
transmitted either by means of facsimile
transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. A copy
of the request for hearing and petition
for leave to intervene should also be
sent to Travis C. McCullough, Assistant
General Counsel, Entergy Nuclear
Operations, Inc., 400 Hamilton Avenue,
White Plains, NY 10601, attorney for the
licensee.
For further details with respect to this
action, see the application for
amendment dated January 15, 2007,
which is available for public inspection
at the Commission’s PDR, located at
One White Flint North, File Public Area
O1 F21, 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. Persons who do not have
access to ADAMS or who encounter
problems in accessing the documents
located in ADAMS, should contact the
NRC PDR Reference staff by telephone
at 1–800–397–4209, 301–415–4737, or
by e-mail to pdr@nrc.gov.
PO 00000
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Fmt 4703
Sfmt 4703
6611
Dated at Rockville, Maryland, this 5th day
of February 2007.
For the Nuclear Regulatory Commission.
James Kim,
Project Manager, Plant Licensing Branch I–
1, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E7–2321 Filed 2–9–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–334 and 50–412]
FirstEnergy Nuclear Operating
Company, Firstenergy Nuclear
Generation Corp.; Ohio Edison
Company; The Toledo Edison
Company; Beaver Valley Power
Station, Unit Nos. 1 and 2;
Environmental Assessment and
Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an amendment to Facility
Operating License Nos. DPR–66 and
NPF–73, issued to the FirstEnergy
Nuclear Operating Company (the
licensee) for operation of the Beaver
Valley Power Station, Unit Nos. 1 and
2 (BVPS–1 and 2), located in Beaver
County, Pennsylvania. Pursuant to Title
10 of the Code of Federal Regulations
(10 CFR) Sections 51.21 and 51.32, the
NRC is issuing this environmental
assessment and finding of no significant
impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would be a
conversion from the current Technical
Specifications (CTSs) to the Improved
Technical Specifications (ITSs) format
based on NUREG–1431, ‘‘Standard
Technical Specifications—
Westinghouse Plants,’’ Revision 2. The
proposed action is in accordance with
the licensee’s application dated
February 25, 2005, as supplemented by
letters dated November 11, 2005, April
19, September 9, October 24, and
December 7, 2006.
The Need for the Proposed Action
The Commission’s ‘‘Proposed Policy
Statement on Technical Specifications
Improvements for Nuclear Power
Reactors’’ (52 FR 3788), dated February
6, 1987, contained an Interim Policy
Statement that set forth objective criteria
for determining which regulatory
requirements and operating restrictions
should be included in the Technical
Specifications (TSs) for nuclear power
plants. When it issued the Interim
Policy Statement, the Commission also
E:\FR\FM\12FEN1.SGM
12FEN1
6612
Federal Register / Vol. 72, No. 28 / Monday, February 12, 2007 / Notices
sroberts on PROD1PC70 with NOTICES
requested comments on it.
Subsequently, to implement the Interim
Policy Statement, each reactor vendor
owners group and the NRC staff began
developing standard TSs (STSs) for
reactors supplied by each vendor. The
Commission then published its ‘‘Final
Policy Statement on Technical
Specifications Improvements for
Nuclear Power Reactors’’ (58 FR 39132),
dated July 22, 1993, in which it
addressed comments received on the
Interim Policy Statement, and
incorporated experience in developing
the STSs. The Final Policy Statement
formed the basis for a revision to 10 CFR
50.36 (60 FR 36953), dated July 19,
1995, that codified the criteria for
determining the content of TSs. The
NRC Committee to Review Generic
Requirements reviewed the STSs, made
note of their safety merits, and indicated
its support of conversion by operating
plants to the STSs. For BVPS–1 and 2,
NUREG–1431 documents the STSs and
forms the basis for the BVPS–1 and 2
conversion to the ITSs.
The proposed changes to the CTSs are
based on NUREG–1431 and the
guidance provided in the Final Policy
Statement. The objective of this action
is to rewrite, reformat, and streamline
the CTSs (i.e., to convert the CTSs to the
ITSs). Emphasis was placed on human
factors principles to improve clarity and
understanding.
Some specifications in the CTSs
would be relocated. Such relocated
specifications would include those
requirements which do not meet the 10
CFR 50.36 selection criteria. These
requirements may be relocated to the TS
Bases document, the BVPS–1 and 2
Updated Final Safety Analysis Report,
the Core Operating Limits Report, the
operational quality assurance plan,
plant procedures, or other licenseecontrolled documents. Relocating
requirements to licensee-controlled
documents does not eliminate them, but
rather places them under more
appropriate regulatory controls (i.e., 10
CFR 50.54(a)(3), and 10 CFR 50.59) to
manage their implementation and future
changes.
Environmental Impacts of the Proposed
Action
The NRC staff has completed its
evaluation of the proposed action and
concludes that the conversion to ITSs
would not increase the probability or
consequences of accidents previously
analyzed and would not affect facility
radiation levels or facility radiological
effluents. The proposed action will not
increase the probability or consequences
of accidents. No changes are being made
in the types of effluents that may be
VerDate Aug<31>2005
19:52 Feb 09, 2007
Jkt 211001
released off site. There is no significant
increase in the amount of any effluent
released off site. There is no significant
increase in occupational or public
radiation exposure. Therefore, there are
no significant radiological
environmental impacts associated with
the proposed action.
With regard to potential nonradiological impacts, the proposed
action does not have a potential to affect
any historic sites because no previously
undisturbed area will be affected by the
proposed amendment. The proposed
action does not affect non-radiological
plant effluents and has no other effect
on the environment. Therefore, there are
no significant non-radiological
environmental impacts associated with
the proposed action.
Accordingly, the NRC staff concludes
that there are no significant
environmental impacts associated with
the proposed action and, thus, the
proposed action will not have any
significant impact to the human
environment.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the NRC staff considered denial
of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the
application would result in no change
in current environmental impacts. Thus,
the environmental impacts of the
proposed action and the alternative
action are similar.
Alternative Use of Resources
The action does not involve the use of
any different resources than those
previously considered in the Final
Environmental Statement for BVPS–1
and 2 dated July 1973 and September
1985, respectively.
Agencies and Persons Consulted
In accordance with its stated policy,
on January 23, 2007, the NRC staff
consulted with the Pennsylvania State
official, Lawrence Ryan, of the
Pennsylvania Department of
Environmental Protection, regarding the
environmental impact of the proposed
action. The State official had no
comments.
Finding of No Significant Impact
On the basis of the environmental
assessment, the NRC concludes that the
proposed action will not have a
significant effect on the quality of the
human environment. Accordingly, the
NRC has determined not to prepare an
environmental impact statement for the
proposed action.
PO 00000
Frm 00096
Fmt 4703
Sfmt 4703
For further details with respect to the
proposed action, see the licensee’s letter
dated June 29, 2005, as supplemented
by letters dated February 25, 2005, as
supplemented by letters dated
November 11, 2005, April 19,
September 9, October 24, and December
7, 2006, and the information provided to
the NRC staff through the joint NRC/
BVPS ITS Conversion web page.
Documents may be examined, and/or
copied for a fee, at the NRC’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 electronically
from the Agencywide Documents
Access and Management System
(ADAMS) Public Electronic Reading
Room on the internet at the NRC Web
site, https://www.nrc.gov/reading-rm/
adams/adams.html. Persons who do not
have access to ADAMS or who
encounter problems in accessing the
documents located in ADAMS, should
contact the NRC PDR Reference staff by
telephone at 1–800–397–4209 or 301–
415–4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 25th day
of January 2007.
For The Nuclear Regulatory Commission.
Nadiyah S. Morgan,
Project Manager, Plant Licensing Branch I–
1, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E7–2373 Filed 2–9–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–259, 50–260, and 50–296]
Tennessee Valley Authority; Browns
Ferry Nuclear Plant; Final
Environmental Assessment and
Finding of No Significant Impact
Related to the Proposed License
Amendment To Increase the Maximum
Reactor Power Level
U.S. Nuclear Regulatory
Commission (NRC).
SUMMARY: The NRC has prepared a final
Environmental Assessment (EA) of its
evaluation of a request by the Tennessee
Valley Authority (TVA) for license
amendments to increase the maximum
thermal power at Browns Ferry Nuclear
Plant (BFN) from 3458 megawattsthermal (MWt) to 3952 MWt for Units 2
and 3 and from 3293 MWt to 3952 MWt
for Unit 1. These represent power
increases of approximately 15 percent
for BFN Units 2 and 3 and 20 percent
for BFN Unit 1. As stated in the NRC
staff’s position paper dated February 8,
AGENCY:
E:\FR\FM\12FEN1.SGM
12FEN1
]]>Agencies
[Federal Register Volume 72, Number 28 (Monday, February 12, 2007)]
[Notices]
[Pages 6611-6612]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-2373]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-334 and 50-412]
FirstEnergy Nuclear Operating Company, Firstenergy Nuclear
Generation Corp.; Ohio Edison Company; The Toledo Edison Company;
Beaver Valley Power Station, Unit Nos. 1 and 2; Environmental
Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an amendment to Facility Operating License Nos. DPR-66 and
NPF-73, issued to the FirstEnergy Nuclear Operating Company (the
licensee) for operation of the Beaver Valley Power Station, Unit Nos. 1
and 2 (BVPS-1 and 2), located in Beaver County, Pennsylvania. Pursuant
to Title 10 of the Code of Federal Regulations (10 CFR) Sections 51.21
and 51.32, the NRC is issuing this environmental assessment and finding
of no significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would be a conversion from the current
Technical Specifications (CTSs) to the Improved Technical
Specifications (ITSs) format based on NUREG-1431, ``Standard Technical
Specifications--Westinghouse Plants,'' Revision 2. The proposed action
is in accordance with the licensee's application dated February 25,
2005, as supplemented by letters dated November 11, 2005, April 19,
September 9, October 24, and December 7, 2006.
The Need for the Proposed Action
The Commission's ``Proposed Policy Statement on Technical
Specifications Improvements for Nuclear Power Reactors'' (52 FR 3788),
dated February 6, 1987, contained an Interim Policy Statement that set
forth objective criteria for determining which regulatory requirements
and operating restrictions should be included in the Technical
Specifications (TSs) for nuclear power plants. When it issued the
Interim Policy Statement, the Commission also
[[Page 6612]]
requested comments on it. Subsequently, to implement the Interim Policy
Statement, each reactor vendor owners group and the NRC staff began
developing standard TSs (STSs) for reactors supplied by each vendor.
The Commission then published its ``Final Policy Statement on Technical
Specifications Improvements for Nuclear Power Reactors'' (58 FR 39132),
dated July 22, 1993, in which it addressed comments received on the
Interim Policy Statement, and incorporated experience in developing the
STSs. The Final Policy Statement formed the basis for a revision to 10
CFR 50.36 (60 FR 36953), dated July 19, 1995, that codified the
criteria for determining the content of TSs. The NRC Committee to
Review Generic Requirements reviewed the STSs, made note of their
safety merits, and indicated its support of conversion by operating
plants to the STSs. For BVPS-1 and 2, NUREG-1431 documents the STSs and
forms the basis for the BVPS-1 and 2 conversion to the ITSs.
The proposed changes to the CTSs are based on NUREG-1431 and the
guidance provided in the Final Policy Statement. The objective of this
action is to rewrite, reformat, and streamline the CTSs (i.e., to
convert the CTSs to the ITSs). Emphasis was placed on human factors
principles to improve clarity and understanding.
Some specifications in the CTSs would be relocated. Such relocated
specifications would include those requirements which do not meet the
10 CFR 50.36 selection criteria. These requirements may be relocated to
the TS Bases document, the BVPS-1 and 2 Updated Final Safety Analysis
Report, the Core Operating Limits Report, the operational quality
assurance plan, plant procedures, or other licensee-controlled
documents. Relocating requirements to licensee-controlled documents
does not eliminate them, but rather places them under more appropriate
regulatory controls (i.e., 10 CFR 50.54(a)(3), and 10 CFR 50.59) to
manage their implementation and future changes.
Environmental Impacts of the Proposed Action
The NRC staff has completed its evaluation of the proposed action
and concludes that the conversion to ITSs would not increase the
probability or consequences of accidents previously analyzed and would
not affect facility radiation levels or facility radiological
effluents. The proposed action will not increase the probability or
consequences of accidents. No changes are being made in the types of
effluents that may be released off site. There is no significant
increase in the amount of any effluent released off site. There is no
significant increase in occupational or public radiation exposure.
Therefore, there are no significant radiological environmental impacts
associated with the proposed action.
With regard to potential non-radiological impacts, the proposed
action does not have a potential to affect any historic sites because
no previously undisturbed area will be affected by the proposed
amendment. The proposed action does not affect non-radiological plant
effluents and has no other effect on the environment. Therefore, there
are no significant non-radiological environmental impacts associated
with the proposed action.
Accordingly, the NRC staff concludes that there are no significant
environmental impacts associated with the proposed action and, thus,
the proposed action will not have any significant impact to the human
environment.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the NRC staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the application would result in no change in current
environmental impacts. Thus, the environmental impacts of the proposed
action and the alternative action are similar.
Alternative Use of Resources
The action does not involve the use of any different resources than
those previously considered in the Final Environmental Statement for
BVPS-1 and 2 dated July 1973 and September 1985, respectively.
Agencies and Persons Consulted
In accordance with its stated policy, on January 23, 2007, the NRC
staff consulted with the Pennsylvania State official, Lawrence Ryan, of
the Pennsylvania Department of Environmental Protection, regarding the
environmental impact of the proposed action. The State official had no
comments.
Finding of No Significant Impact
On the basis of the environmental assessment, the NRC concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the NRC has determined
not to prepare an environmental impact statement for the proposed
action.
For further details with respect to the proposed action, see the
licensee's letter dated June 29, 2005, as supplemented by letters dated
February 25, 2005, as supplemented by letters dated November 11, 2005,
April 19, September 9, October 24, and December 7, 2006, and the
information provided to the NRC staff through the joint NRC/BVPS ITS
Conversion web page. Documents may be examined, and/or copied for a
fee, at the NRC'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 electronically from the Agencywide Documents Access and
Management System (ADAMS) Public Electronic Reading Room on the
internet at the NRC Web site, https://www.nrc.gov/reading-rm/adams/
adams.html. Persons who do not have access to ADAMS or who encounter
problems in accessing the documents located in ADAMS, should contact
the NRC PDR Reference staff by telephone at 1-800-397-4209 or 301-415-
4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 25th day of January 2007.
For The Nuclear Regulatory Commission.
Nadiyah S. Morgan,
Project Manager, Plant Licensing Branch I-1, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E7-2373 Filed 2-9-07; 8:45 am]
BILLING CODE 7590-01-P
