FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station, Unit No. 1; Environmental Assessment and Finding of No Significant Impact, 62343-62344 [E8-24899]
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Federal Register / Vol. 73, No. 203 / Monday, October 20, 2008 / Notices
Dated: October 14, 2008.
G. Paul Bollwerk, III,
Chairman, Rockville, Maryland.
[FR Doc. E8–24892 Filed 10–17–08; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–346]
FirstEnergy Nuclear Operating
Company; Davis-Besse Nuclear Power
Station, Unit No. 1; Environmental
Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory
Commission (the Commission, NRC) is
considering issuance of an amendment
for Facility Operating License No. NPF–
3, issued to FirstEnergy Nuclear
Operating Company (the licensee,
FENOC), for operation of the DavisBesse Nuclear Power Station, Unit No.
1 (DBNPS) located in Ottawa County,
Ohio. 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.
The Notice of Consideration of Issuance
of Amendment was published in the
Federal Register (FR) on May 22, 2008
(73 FR 29787).
mstockstill on PROD1PC66 with NOTICES
Environmental Assessment
Identification of the Proposed Action
The proposed action would be a full
conversion from the current technical
specifications (CTS) to the improved
technical specifications (ITS) consistent
with improved standard technical
specifications as described in ‘‘Standard
Technical Specifications Babcock and
Wilcox Plants,’’ Revision 3.0 (STS)
(Agencywide Documents Access and
Management System (ADAMS)
Accession No. ML041800598). STS
Revision 3.0 consists of the following
NRC approved TS Task Force Travelers
(TSTFS) TSTF–369 Revision 1, TSTF–
372 Revision 4, TSTF–400 Revision 1,
TSTF–439 Revision 2, TSTF–449
Revision 4, TSTF–479 Revision 0,
TSTF–482 Revision 0, and TSTF–485
Revision 0. The proposed action also
encompasses the beyond scope issues
included in the Notice of Consideration
of Issuance of Amendment.
The proposed action is in accordance
with the licensee’s application dated
August 3, 2007 (ADAMS Accession No.
ML072200448), as supplemented by
letters dated May 16, 2008 (2 letters)
(ADAMS Accession Nos. ML081480464
and ML081430105), July 23, 2008
(ADAMS Accession No. ML082070079),
VerDate Aug<31>2005
16:42 Oct 17, 2008
Jkt 217001
August 7, 2008 (ADAMS Accession No.
ML082270658), August 26, 2008
(ADAMS Accession No. ML082600594),
and September 3, 2008 (ADAMS
Accession No. ML082490154). The
information provided to the Nuclear
Regulatory Commission (NRC) staff
through the joint NRC-FirstEnergy
Nuclear Operating Company improved
technical specifications (ITS)
conversion web page hosted by Excel
Services Corporation can be found in
these supplements. To expedite its
review of the application, the NRC staff
issued its requests for additional
information (RAI) through the DBNPS
ITS Conversion web page and the
licensee addressed the RAI by providing
responses on the web page. Entry into
the database is protected so that only
the licensee and NRC reviewers can
enter information into the database to
add RAIs (NRC) or provide responses to
the RAIs (licensee); however, the public
can enter the database to read the
questions asked and the responses
provided. To be in compliance with the
regulations for written communications
for license amendment requests, and to
have the database on the DBNPS
dockets before the amendment is issued,
the licensee will submit a copy of the
database in a submittal to the NRC after
there are no further RAIs and before the
amendment is issued. The public can
access the Web site by going to https://
www.excelservices.com. Once at the
Web site, click on ‘‘Davis Besse’’ on the
left side of the screen. Upon clicking the
link, the Web site will inform you that
‘‘you are about to enter the DAVIS
BESSE Improved Technical
Specification Licensing On-Line
Question and Answer Database.’’ At this
point, click on ‘‘Click Here to continue.’’
This will bring you to the ITS Licensing
Database. The RAIs and responses to
RAIs are organized by ITS Sections 1.0,
2.0, 3.0, 3.1 through 3.9, 4.0, and 5.0.
For every listed ITS section, there is a
RAI which can be read by clicking on
the ITS section number. The RAI
question(s) and the licensee’s
response(s) are contained on the same
web page.
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 (TS). When it issued the
Interim Policy Statement, the
Commission also requested comments
PO 00000
Frm 00098
Fmt 4703
Sfmt 4703
62343
on it. Subsequently, to implement the
Interim Policy Statement, each reactor
vendor owners group and the NRC staff
began developing STS 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 STS. 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 TS. The NRC Committee to
Review Generic Requirements reviewed
the STS, made note of their safety
merits, and indicated its support of
conversion by operating plants to the
STS. For DBNPS, NUREG–1430
Revision 3.0 and the following NRC
approved TSTF–369 Revision 1, TSTF–
372 Revision 4, TSTF–400 Revision 1,
TSTF–439 Revision 2, TSTF–449
Revision 4, TSTF–479 Revision 0,
TSTF–482 Revision 0, and TSTF–485
Revision 0, document the STS and form
the basis for DBNPS conversion to the
ITS.
The proposed changes to the CTS are
based on NUREG–1430 and the
guidance provided in the Final Policy
Statement. The objective of this action
is to rewrite, reformat, and streamline
the CTS (i.e., to convert the CTS to the
ITS). Emphasis was placed on human
factors principles to improve clarity and
understanding. The ITS Bases section
has been significantly expanded to
clarify and better explain the purpose
and foundation of each specification. In
addition to NUREG–1430, portions of
the CTS were also used as the basis for
the development of the DBNPS ITS. The
NRC staff discussed plant-specific
issues (i.e., unique design features,
requirements, and operating practices)
with the licensee.
Relocated specifications include those
changes to the CTS that relocate certain
requirements which do not meet the 10
CFR 50.36 selection criteria. These
requirements may be relocated to the
Bases section, updated safety analysis
report, core operating limits report,
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.
E:\FR\FM\20OCN1.SGM
20OCN1
62344
Federal Register / Vol. 73, No. 203 / Monday, October 20, 2008 / Notices
The proposed action is necessary to
allow the licensee to implement the ITS.
The ITS are based on standard Babcock
and Wilcox TSs. They are considered an
improvement over the CTS.
Environmental Impacts of the Proposed
Action
The NRC has completed its safety
evaluation of the proposed action and
concludes that the proposed TS
conversion would not increase the
probability or consequences of accidents
previously analyzed and would not
affect facility radiation levels or facility
radiological effluents due to the fact that
no physical facility is being affected.
The details of the staff’s safety
evaluation will be provided in the
license amendment. Specifically, the
proposed TS changes will not increase
the probability or consequences of
accidents. No changes are being made in
the types or amounts of any effluent that
may be released offsite, and there is no
significant increase in the allowable
individual or cumulative occupational
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 TS changes. It does not affect
nonradiological plant effluents and has
no other environmental impact. No
physical facility is being affected by this
change. Therefore, there are no
significant nonradiological
environmental impacts associated with
the proposed action. Accordingly, the
NRC 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.
mstockstill on PROD1PC66 with NOTICES
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the 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. 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 the
DBNPS, dated October 31, 1975.
VerDate Aug<31>2005
16:42 Oct 17, 2008
Jkt 217001
Agencies and Persons Consulted
On July 14, 2008, the NRC staff
consulted with the Ohio State official,
Carol O’Claire of the Department of
Public Safety, 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 August 3, 2007 (ADAMS
Accession No. ML072200448), as
supplemented by letters dated May 16,
2008 (2 letters) (ADAMS Accession Nos.
ML081480464 and ML081430105), July
23, 2008 (ADAMS Accession No.
ML082070079), August 7, 2008
(ADAMS Accession No. ML082270658),
August 26, 2008 (ADAMS Accession
No. ML082600594), and September 3,
2008 (ADAMS Accession No.
ML082490154). The information
provided to the Nuclear Regulatory
Commission (NRC) staff through the
joint NRC-FirstEnergy Nuclear
Operating Company improved technical
specifications (ITS) conversion web
page hosted by Excel Services
Corporation can be found in these
supplements. 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 O1 F21, 11555 Rockville Pike
(first floor), Rockville, Maryland.
Publicly available records will be
accessible electronically 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 or 301–415–4737, or
send an e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 8th day
of October 2008.
For the Nuclear Regulatory Commission.
Cameron S. Goodwin,
Project Manager, Plant Licensing Branch III–
2, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E8–24899 Filed 10–17–08; 8:45 am]
BILLING CODE 7590–01–P
PO 00000
Frm 00099
Fmt 4703
Sfmt 4703
SECURITIES AND EXCHANGE
COMMISSION
[Release No. 34–58765; File No. 4–551]
Program for Allocation of Regulatory
Responsibilities Pursuant to Rule 17d–
2; Notice of Filing and Order
Approving and Declaring Effective an
Amendment to the Plan for the
Allocation of Regulatory
Responsibilities Among the American
Stock Exchange LLC, Boston Stock
Exchange, Inc., Chicago Board
Options Exchange, Incorporated,
International Securities Exchange,
LLC, Financial Industry Regulatory
Authority, Inc., The NASDAQ Stock
Market LLC, NYSE Arca, Inc., and
NASDAQ OMX PHLX, Inc., Relating to
Options Market Surveillance
October 9, 2008.
Notice is hereby given that the
Securities and Exchange Commission
(‘‘Commission’’) has issued an Order,
pursuant to Section 17(d) of the
Securities Exchange Act of 1934
(‘‘Act’’),1 approving and declaring
effective an amendment to the plan for
allocating regulatory responsibility
(‘‘Plan’’) filed pursuant to Rule 17d–2 of
the Act,2 by the American Stock
Exchange LLC (‘‘Amex’’), Boston Stock
Exchange, Inc. (‘‘BSE’’), Chicago Board
Options Exchange, Incorporated
(‘‘CBOE’’), International Securities
Exchange, LLC (‘‘ISE’’), Financial
Industry Regulatory Authority, Inc.
(‘‘FINRA’’), The NASDAQ Stock Market
LLC (‘‘NASDAQ’’), NYSE Arca, Inc.
(‘‘NYSE Arca’’), and NASDAQ OMX
PHLX, Inc. (‘‘Phlx’’) (collectively, ‘‘SRO
Participants’’) concerning optionsrelated market surveillance.
I. Introduction
Section 19(g)(1) of the Act,3 among
other things, requires every selfregulatory organization (‘‘SRO’’)
registered as either a national securities
exchange or national securities
association to examine for, and enforce
compliance by, its members and persons
associated with its members with the
Act, the rules and regulations
thereunder, and the SRO’s own rules,
unless the SRO is relieved of this
responsibility pursuant to Section
17(d) 4 or Section 19(g)(2) 5 of the Act.
Without this relief, the statutory
obligation of each individual SRO could
result in a pattern of multiple
examinations of broker-dealers that
1 15
U.S.C. 78q(d).
CFR 240.17d–2.
3 15 U.S.C. 78s(g)(1).
4 15 U.S.C. 78q(d).
5 15 U.S.C. 78s(g)(2).
2 17
E:\FR\FM\20OCN1.SGM
20OCN1
]]>Agencies
[Federal Register Volume 73, Number 203 (Monday, October 20, 2008)]
[Notices]
[Pages 62343-62344]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-24899]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-346]
FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power
Station, Unit No. 1; Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission, NRC) is
considering issuance of an amendment for Facility Operating License No.
NPF-3, issued to FirstEnergy Nuclear Operating Company (the licensee,
FENOC), for operation of the Davis-Besse Nuclear Power Station, Unit
No. 1 (DBNPS) located in Ottawa County, Ohio. 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. The Notice of Consideration of Issuance of
Amendment was published in the Federal Register (FR) on May 22, 2008
(73 FR 29787).
Environmental Assessment
Identification of the Proposed Action
The proposed action would be a full conversion from the current
technical specifications (CTS) to the improved technical specifications
(ITS) consistent with improved standard technical specifications as
described in ``Standard Technical Specifications Babcock and Wilcox
Plants,'' Revision 3.0 (STS) (Agencywide Documents Access and
Management System (ADAMS) Accession No. ML041800598). STS Revision 3.0
consists of the following NRC approved TS Task Force Travelers (TSTFS)
TSTF-369 Revision 1, TSTF-372 Revision 4, TSTF-400 Revision 1, TSTF-439
Revision 2, TSTF-449 Revision 4, TSTF-479 Revision 0, TSTF-482 Revision
0, and TSTF-485 Revision 0. The proposed action also encompasses the
beyond scope issues included in the Notice of Consideration of Issuance
of Amendment.
The proposed action is in accordance with the licensee's
application dated August 3, 2007 (ADAMS Accession No. ML072200448), as
supplemented by letters dated May 16, 2008 (2 letters) (ADAMS Accession
Nos. ML081480464 and ML081430105), July 23, 2008 (ADAMS Accession No.
ML082070079), August 7, 2008 (ADAMS Accession No. ML082270658), August
26, 2008 (ADAMS Accession No. ML082600594), and September 3, 2008
(ADAMS Accession No. ML082490154). The information provided to the
Nuclear Regulatory Commission (NRC) staff through the joint NRC-
FirstEnergy Nuclear Operating Company improved technical specifications
(ITS) conversion web page hosted by Excel Services Corporation can be
found in these supplements. To expedite its review of the application,
the NRC staff issued its requests for additional information (RAI)
through the DBNPS ITS Conversion web page and the licensee addressed
the RAI by providing responses on the web page. Entry into the database
is protected so that only the licensee and NRC reviewers can enter
information into the database to add RAIs (NRC) or provide responses to
the RAIs (licensee); however, the public can enter the database to read
the questions asked and the responses provided. To be in compliance
with the regulations for written communications for license amendment
requests, and to have the database on the DBNPS dockets before the
amendment is issued, the licensee will submit a copy of the database in
a submittal to the NRC after there are no further RAIs and before the
amendment is issued. The public can access the Web site by going to
https://www.excelservices.com. Once at the Web site, click on ``Davis
Besse'' on the left side of the screen. Upon clicking the link, the Web
site will inform you that ``you are about to enter the DAVIS BESSE
Improved Technical Specification Licensing On-Line Question and Answer
Database.'' At this point, click on ``Click Here to continue.'' This
will bring you to the ITS Licensing Database. The RAIs and responses to
RAIs are organized by ITS Sections 1.0, 2.0, 3.0, 3.1 through 3.9, 4.0,
and 5.0. For every listed ITS section, there is a RAI which can be read
by clicking on the ITS section number. The RAI question(s) and the
licensee's response(s) are contained on the same web page.
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 (TS). When it issued the Interim Policy Statement, the
Commission also requested comments on it. Subsequently, to implement
the Interim Policy Statement, each reactor vendor owners group and the
NRC staff began developing STS 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
STS. 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 TS. The NRC Committee to Review
Generic Requirements reviewed the STS, made note of their safety
merits, and indicated its support of conversion by operating plants to
the STS. For DBNPS, NUREG-1430 Revision 3.0 and the following NRC
approved TSTF-369 Revision 1, TSTF-372 Revision 4, TSTF-400 Revision 1,
TSTF-439 Revision 2, TSTF-449 Revision 4, TSTF-479 Revision 0, TSTF-482
Revision 0, and TSTF-485 Revision 0, document the STS and form the
basis for DBNPS conversion to the ITS.
The proposed changes to the CTS are based on NUREG-1430 and the
guidance provided in the Final Policy Statement. The objective of this
action is to rewrite, reformat, and streamline the CTS (i.e., to
convert the CTS to the ITS). Emphasis was placed on human factors
principles to improve clarity and understanding. The ITS Bases section
has been significantly expanded to clarify and better explain the
purpose and foundation of each specification. In addition to NUREG-
1430, portions of the CTS were also used as the basis for the
development of the DBNPS ITS. The NRC staff discussed plant-specific
issues (i.e., unique design features, requirements, and operating
practices) with the licensee.
Relocated specifications include those changes to the CTS that
relocate certain requirements which do not meet the 10 CFR 50.36
selection criteria. These requirements may be relocated to the Bases
section, updated safety analysis report, core operating limits report,
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.
[[Page 62344]]
The proposed action is necessary to allow the licensee to implement
the ITS. The ITS are based on standard Babcock and Wilcox TSs. They are
considered an improvement over the CTS.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
and concludes that the proposed TS conversion would not increase the
probability or consequences of accidents previously analyzed and would
not affect facility radiation levels or facility radiological effluents
due to the fact that no physical facility is being affected. The
details of the staff's safety evaluation will be provided in the
license amendment. Specifically, the proposed TS changes will not
increase the probability or consequences of accidents. No changes are
being made in the types or amounts of any effluent that may be released
offsite, and there is no significant increase in the allowable
individual or cumulative occupational 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 TS
changes. It does not affect nonradiological plant effluents and has no
other environmental impact. No physical facility is being affected by
this change. Therefore, there are no significant nonradiological
environmental impacts associated with the proposed action. Accordingly,
the NRC 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 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. 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
the DBNPS, dated October 31, 1975.
Agencies and Persons Consulted
On July 14, 2008, the NRC staff consulted with the Ohio State
official, Carol O'Claire of the Department of Public Safety, 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 August 3, 2007 (ADAMS Accession No.
ML072200448), as supplemented by letters dated May 16, 2008 (2 letters)
(ADAMS Accession Nos. ML081480464 and ML081430105), July 23, 2008
(ADAMS Accession No. ML082070079), August 7, 2008 (ADAMS Accession No.
ML082270658), August 26, 2008 (ADAMS Accession No. ML082600594), and
September 3, 2008 (ADAMS Accession No. ML082490154). The information
provided to the Nuclear Regulatory Commission (NRC) staff through the
joint NRC-FirstEnergy Nuclear Operating Company improved technical
specifications (ITS) conversion web page hosted by Excel Services
Corporation can be found in these supplements. 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 O1 F21, 11555
Rockville Pike (first floor), Rockville, Maryland. Publicly available
records will be accessible electronically 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 or 301-415-4737, or send an e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 8th day of October 2008.
For the Nuclear Regulatory Commission.
Cameron S. Goodwin,
Project Manager, Plant Licensing Branch III-2, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E8-24899 Filed 10-17-08; 8:45 am]
BILLING CODE 7590-01-P
