Nuclear Management Company, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact, 30819-30820 [E5-2688]
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Federal Register / Vol. 70, No. 102 / Friday, May 27, 2005 / Notices
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Comments can also be e-mailed to
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submitted by telephone at (202) 395–
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Jo. Shelton, 301–415–7233.
Dated at Rockville, Maryland, this 23rd day
of May, 2005.
For the Nuclear Regulatory Commission.
Brenda Jo. Shelton,
NRC Clearance Officer, Office of the Chief
Information Officer.
[FR Doc. E5–2689 Filed 5–26–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
The petition is being treated pursuant
to 10 CFR 2.206 of the Commission’s
regulations. The petition has been
referred to the Director of the Office of
Nuclear Reactor Regulation. As
provided by Section 2.206, appropriate
action will be taken on this petition
within a reasonable time. Mr. Lochbaum
declined to meet with or participate in
a telephone conference with the Petition
Review Board on this matter stating that
all pertinent facts were contained
within his petition. Copies of the
petition are available for inspection at
the Commission’s Public Document
Room, located at One White Flint North,
Public File Area O–1F21, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible 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.html (Accession No.
ML051100297). Persons who do not
have access to 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.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland this 20th day
of May 2005.
J. E. Dyer,
Director, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–2687 Filed 5–26–05; 8:45 am]
BILLING CODE 7590–01–P
[Docket Nos. 50–334 AND 50–412 and
License Nos. DPR–66 and NPF–73]
FirstEnergy Nuclear Operating
Company (FENOC) Receipt of Request
for Action Under 10 CFR 2.2206
Notice is hereby given that by petition
dated April 12, 2005, Mr. David
Lochbaum of the Union of Concerned
Scientists requested that the Nuclear
Regulatory Commission (NRC) take
action with regard to Beaver Valley
Power Station, Unit Nos. 1 and 2. The
petitioner requests that the NRC take
enforcement action against FENOC and
impose a civil penalty of at least
$55,000.
As the basis for this request, the
petitioner states that the licensee’s
February 9, 2005, license renewal
submittal was not complete and
accurate in all material respects and that
this is a violation of 10 CFR 50.9,
paragraph (a) which requires in part,
that information provided to the
Commission by a licensee shall be
complete and accurate in all material
respects.
VerDate jul<14>2003
16:42 May 26, 2005
Jkt 205001
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–266 and 50–301]
Nuclear Management Company, LLC;
Point Beach Nuclear Plant, Units 1 and
2; Environmental Assessment and
Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption from Title 10
of the Code of Federal Regulations (10
CFR) Part 50, Appendix R, Section
IlI.G.1.a for Facility Operating License
Nos. DPR–24 and DPR–27, issued to
Nuclear Management Company, LLC
(NMC), the licensee, for operation of the
Point Beach Nuclear Plant (PBNP),
Units 1 and 2, located in Manitowoc
County, Wisconsin. Therefore, as
required by 10 CFR 51.21, the NRC is
issuing this environmental assessment
and finding of no significant impact.
PO 00000
Frm 00145
Fmt 4703
Sfmt 4703
30819
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt
10 CFR Part 50, Appendix R, Section
III.G.1.a as it applies to the PBNP, Unit
1 auxiliary and turbine buildings; and
the PBNP, Unit 2 auxiliary and turbine
buildings, and the control building. The
exemption requested is from the
requirement that, ‘‘one train of systems
necessary to achieve and maintain hot
shutdown from either the control room
or emergency control station(s) is free of
fire damage,’’ as it applies to the PBNP,
Unit 1 auxiliary and turbine buildings;
the PBNP, Unit 2 auxiliary and turbine
buildings, and the control building.
Specifically, NMC has asked for a repair
consisting of powering a dedicated air
compressor from one of two preplanned 480 volt power sources using
pre-staged power cords and connecting
the air compressor to nitrogen bottle
manifolds on one or both reactor units
using pre-staged pneumatic hose with
quick connect fittings. The repair would
be required no earlier than 8 hours into
an event in which instrument air is
disabled.
The proposed action is in accordance
with the licensee’s application dated
March 5, 2004, as supplemented by
letter dated November 8, 2004.
The Need for the Proposed Action
Appendix R, Section Ill.G.1.a of 10
CFR Part 50 requires that, ‘‘one train of
systems necessary to achieve and
maintain hot shutdown conditions from
either the control room or emergency
control station(s) is free of fire damage.’’
Appendix R, Section Ill.L.1 of 10 CFR
Part 50 requires that an alternative or
dedicated shutdown capability shall be
able to, among other things, ‘‘(c) achieve
and maintain hot standby conditions for
a pressurized water reactor (PWR)’’; and
‘‘(d) achieve cold shutdown conditions
within 72 hours.’’ NRC Inspection
Report 50–266/2003–007; 50–301/2003–
007, dated February 4, 2004, documents
a Non-Cited Violation of Appendix R,
Section III.L.1.c, in that NMC, ‘‘failed to
ensure, without the need for ’hot
standby repairs,’ adequate control air to
the speed controllers for the charging
pumps during a postulated fire
requiring an alternative shutdown
method.’’ The installed backup nitrogen
gas bottle bank (for the charging pump
speed controllers) meets the
requirements of the regulation, with the
exception that it is of limited capacity.
This means that the hot shutdown
conditions could not be maintained
indefinitely while relying only on the
installed bottle bank. However, the 8 to
14 hour capacity of the bottle banks is
E:\FR\FM\27MYN1.SGM
27MYN1
30820
Federal Register / Vol. 70, No. 102 / Friday, May 27, 2005 / Notices
ample time to extinguish the fire,
achieve stable plant conditions in hot
shutdown, augment staff with personnel
from the emergency response
organization, and connect dedicated
power cabling and hoses to the
dedicated compressor using the
furnished plugs and quick connect
fittings (i.e., no tools required).
Because the bottle banks, hoses,
cables, and compressor are all located in
areas that would not be affected by the
fires of concern, none would be
damaged. Thus, the proposed
exemption is fully consistent with the
intent of the applicable sections of 10
CFR Part 50, Appendix R, and literal
compliance is not necessary to achieve
the underlying purpose of the rules.
Environmental Impacts of the Proposed
Action
The NRC has completed its safety
evaluation of the proposed action and
concludes that pursuant to 10 CFR
50.12(a)(2)(ii), the level of fire safety
provided is equivalent to the technical
requirements of 10 CFR Part 50
Appendix R, Section IlI.G.1.a. As such,
the requested exemption does not pose
an undue risk to the health and safety
of the public.
The details of the NRC staff’s safety
evaluation will be provided in the
exemption that will be issued as part of
the letter to the licensee approving the
exemption to the regulation.
The proposed action will not
significantly 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 nonradiological impacts, the proposed
action does not have a potential to affect
any historic sites. It does not affect nonradiological plant effluents and has no
other environmental impact. Therefore,
there are no significant non-radiological
environmental impacts associated with
the proposed action.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action.
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
VerDate jul<14>2003
16:42 May 26, 2005
Jkt 205001
application would result in no change
in current environmental impacts. The
environmental impacts of the proposed
action and the alternative action are
similar.
NUCLEAR REGULATORY
COMMISSION
Alternative Use of Resources
Atomic Safety and Licensing Board; In
the Matter of U.S. Department of
Energy (High Level Waste Repository:
Pre-Application Matters)
The action does not involve the use of
any different resources than those
previously considered in the Final
Environmental Statement for the Point
Beach Nuclear Plant, Units 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy,
on April 4, 2005, the NRC staff
consulted with the Wisconsin State
official, Jeffery Kitsembel of the Public
Service Commission of Wisconsin,
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 March 5, 2004, as supplemented
by letter dated November 8, 2004.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, 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.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 23rd day
of May, 2005.
For the Nuclear Regulatory Commission.
Harold K. Chernoff,
Project Manager, Section 1, Project
Directorate III, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–2688 Filed 5–26–05; 8:45 am]
BILLING CODE 7590–01–P
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Frm 00146
Fmt 4703
Sfmt 4703
[Docket No. PAPO–00; ASLBP No. 04–829–
01–PAPO]
May 23, 2005.
Before Administrative Judges: Thomas
S. Moore, Chairman, Alex S. Karlin
Alan S. Rosenthal.
Order
The Pre-License Application
Presiding Officer (PAPO) Board held its
second case management conference in
this proceeding on May 18, 2005. The
Department of Energy (DOE), the NRC
Staff, the State of Nevada (State), the
Nuclear Energy Institute (NEI), and the
Nuclear Information and Research
Service (NIRS) attended the conference.
During this meeting the Board heard
discussion on a written request, filed by
DOE on May 12, 2005, that the Board
establish uniform requirements for the
retention of e-mails and other
documents that constitute or may
constitute documentary material as
defined in 10 CFR 2.1001. DOE
suggested that document retention
requirements should be part of the
procedures required under 10 CFR
2.1009, and that participation as a party
in this proceeding requires substantial
compliance with such procedures under
10 CFR 2.1012(b). DOE, the NRC Staff,
the State, and NIRS participated in the
discussion of this proposal.
Upon consideration of this matter,
and hearing no objection from any of the
participants during the May 18, 2005
conference, the Board agreed that the
matter warranted further consideration
and attention. The Board is concerned
that, absent a uniform procedure
prescribed by a case management order,
some of the current participants, as well
as other potential parties, might not
have timely instituted documentary
material retention policies or been
aware of the need to adopt and follow
retention policies for such material. The
development and specification at this
time of reasonable uniform
documentary material retention
procedures should enable all current
participants and potential parties to
avoid unnecessary burdens and
expense.
Accordingly, the Board orders the
participants attending the second case
management conference to meet and to
confer for the purpose of developing a
joint proposed minimum acceptable
E:\FR\FM\27MYN1.SGM
27MYN1
Agencies
[Federal Register Volume 70, Number 102 (Friday, May 27, 2005)]
[Notices]
[Pages 30819-30820]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-2688]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-266 and 50-301]
Nuclear Management Company, LLC; Point Beach Nuclear Plant, Units
1 and 2; Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption from Title 10 of the Code of Federal
Regulations (10 CFR) Part 50, Appendix R, Section IlI.G.1.a for
Facility Operating License Nos. DPR-24 and DPR-27, issued to Nuclear
Management Company, LLC (NMC), the licensee, for operation of the Point
Beach Nuclear Plant (PBNP), Units 1 and 2, located in Manitowoc County,
Wisconsin. Therefore, as required by 10 CFR 51.21, the NRC is issuing
this environmental assessment and finding of no significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt 10 CFR Part 50, Appendix R,
Section III.G.1.a as it applies to the PBNP, Unit 1 auxiliary and
turbine buildings; and the PBNP, Unit 2 auxiliary and turbine
buildings, and the control building. The exemption requested is from
the requirement that, ``one train of systems necessary to achieve and
maintain hot shutdown from either the control room or emergency control
station(s) is free of fire damage,'' as it applies to the PBNP, Unit 1
auxiliary and turbine buildings; the PBNP, Unit 2 auxiliary and turbine
buildings, and the control building. Specifically, NMC has asked for a
repair consisting of powering a dedicated air compressor from one of
two pre-planned 480 volt power sources using pre-staged power cords and
connecting the air compressor to nitrogen bottle manifolds on one or
both reactor units using pre-staged pneumatic hose with quick connect
fittings. The repair would be required no earlier than 8 hours into an
event in which instrument air is disabled.
The proposed action is in accordance with the licensee's
application dated March 5, 2004, as supplemented by letter dated
November 8, 2004.
The Need for the Proposed Action
Appendix R, Section Ill.G.1.a of 10 CFR Part 50 requires that,
``one train of systems necessary to achieve and maintain hot shutdown
conditions from either the control room or emergency control station(s)
is free of fire damage.'' Appendix R, Section Ill.L.1 of 10 CFR Part 50
requires that an alternative or dedicated shutdown capability shall be
able to, among other things, ``(c) achieve and maintain hot standby
conditions for a pressurized water reactor (PWR)''; and ``(d) achieve
cold shutdown conditions within 72 hours.'' NRC Inspection Report 50-
266/2003-007; 50-301/2003-007, dated February 4, 2004, documents a Non-
Cited Violation of Appendix R, Section III.L.1.c, in that NMC, ``failed
to ensure, without the need for 'hot standby repairs,' adequate control
air to the speed controllers for the charging pumps during a postulated
fire requiring an alternative shutdown method.'' The installed backup
nitrogen gas bottle bank (for the charging pump speed controllers)
meets the requirements of the regulation, with the exception that it is
of limited capacity. This means that the hot shutdown conditions could
not be maintained indefinitely while relying only on the installed
bottle bank. However, the 8 to 14 hour capacity of the bottle banks is
[[Page 30820]]
ample time to extinguish the fire, achieve stable plant conditions in
hot shutdown, augment staff with personnel from the emergency response
organization, and connect dedicated power cabling and hoses to the
dedicated compressor using the furnished plugs and quick connect
fittings (i.e., no tools required).
Because the bottle banks, hoses, cables, and compressor are all
located in areas that would not be affected by the fires of concern,
none would be damaged. Thus, the proposed exemption is fully consistent
with the intent of the applicable sections of 10 CFR Part 50, Appendix
R, and literal compliance is not necessary to achieve the underlying
purpose of the rules.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
and concludes that pursuant to 10 CFR 50.12(a)(2)(ii), the level of
fire safety provided is equivalent to the technical requirements of 10
CFR Part 50 Appendix R, Section IlI.G.1.a. As such, the requested
exemption does not pose an undue risk to the health and safety of the
public.
The details of the NRC staff's safety evaluation will be provided
in the exemption that will be issued as part of the letter to the
licensee approving the exemption to the regulation.
The proposed action will not significantly 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. It does
not affect non-radiological plant effluents and has no other
environmental impact. Therefore, there are no significant non-
radiological environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
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. 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 Point Beach Nuclear Plant, Units 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy, on April 4, 2005, the NRC
staff consulted with the Wisconsin State official, Jeffery Kitsembel of
the Public Service Commission of Wisconsin, 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 March 5, 2004, as supplemented by letter dated
November 8, 2004. Documents may be examined, and/or copied for a fee,
at the NRC's Public Document Room (PDR), located at One White Flint
North, 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.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 23rd day of May, 2005.
For the Nuclear Regulatory Commission.
Harold K. Chernoff,
Project Manager, Section 1, Project Directorate III, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-2688 Filed 5-26-05; 8:45 am]
BILLING CODE 7590-01-P