Carolina Power & Light Company, Brunswick Steam Electric Plant, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact, 11034-11035 [05-4312]
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Federal Register / Vol. 70, No. 43 / Monday, March 7, 2005 / Notices
Dated: March 2, 2005.
Kathy Plowitz-Worden,
Panel Coordinator, Panel Operations,
National Endowment for the Arts.
[FR Doc. 05–4331 Filed 3–4–05; 8:45 am]
BILLING CODE 7537–01–P
NATIONAL SCIENCE FOUNDATION
NSF–NASA Astronomy and
Astrophysics Advisory Committee
#13883; Notice of Meeting
In accordance with the Federal
Advisory Committee Act (Pub. L. 92–
463, as amended), the National Science
Foundation announces the following
NSF–NASA Astronomy and
Astrophysics Advisory Committee
(#13883) meeting:
Date and Time: March 9, 2005, 2:30 a.m.–
4:30 p.m.
Place: National Science Foundation, 4201
Wilson Blvd. RM 1020, Arlington, VA 22230,
via teleconference.
Type of Meeting: Open.
Contact Person: Dr. G. Wayne Van Citters,
Director, Division of Astronomical Sciences,
Suite 1045, National Science Foundation,
4201 Wilson Blvd., Arlington, VA 22230.
Telephone: 703–292–4908.
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members realized additional discussion was
required. To meet the report deadline of
March 15, a meeting with little advance
notice is required.
Dated: March 2, 2005.
Susanne E. Bolton,
Committee Management Officer.
[FR Doc. 05–4352 Filed 3–4–05; 8:45 am]
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Place: National Science Foundation,
Arlington, Virginia.
Type of Meeting: Closed.
Contact Person: Mrs. Susan E. Fannoney,
Executive Secretary, National Science Board
Office, National Science Foundation, 4201
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552b(c)(6) of the Government in the Sunshine
Act.
Dated: March 2, 2005.
Susanne Bolton,
Committee Management Officer.
[FR Doc. 05–4351 Filed 3–4–05; 8:45 am]
BILLING CODE 7555–01–M
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–325 and 50–324]
Carolina Power & Light Company,
Brunswick Steam Electric Plant, Unit
Nos. 1 and 2; Environmental
Assessment and Finding of No
Significant Impact
Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption from 10 CFR
Part 50, Appendix J for Facility
Operating Licenses Nos. DPR–71 and
DPR–62 issued to the Carolina Power &
Light Company (the licensee, also doing
business as Progress Energy Carolinas,
Inc.) for operation of the Brunswick
Steam Electric Plant, Unit Nos. 1 and 2
located in Brunswick County, North
Carolina.
Environmental Assessment
Identification of the Proposed Action
NATIONAL SCIENCE FOUNDATION
National Science Board Public Service
Award Committee; Notice of Meeting
In accordance with the Federal
Advisory Committee Act (Pub. L. 92–
463, as amended), the National Science
Foundation announces the following
meeting:
Name: National Science Board Public
Service Award Committee, #5195.
Date and Time: Thursday, March 24, 10:30
a.m.–11:30 a.m. e.s.t. (teleconference
meeting).
VerDate jul<14>2003
18:15 Mar 04, 2005
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The proposed action would exempt
the licensee from requirements to
include main steam isolation valve
(MSIV) leakage in the overall integrated
leakage rate test measurement required
by Section III.A of Appendix J, Option
B.
The proposed action is in accordance
with the licensee’s application dated
October 6, 2004, for exemption from
certain requirements of Title 10 of the
Code of Federal Regulations (10 CFR),
Part 50, Appendix J.
PO 00000
Frm 00100
Fmt 4703
Sfmt 4703
The Need for the Proposed Action
Section 50.54(o) of 10 CFR Part 50
requires that primary reactor
containments for water-cooled power
reactors be subject to the requirements
of Appendix J to 10 CFR Part 50.
Appendix J specifies the leakage test
requirements, schedules, and
acceptance criteria for tests of the
leaktight integrity of the primary reactor
containment and systems and
components that penetrate the
containment. Option B, Section III.A
requires that the overall integrated leak
rate must not exceed the allowable
leakage (La) with margin, as specified in
the Technical Specifications (TS). The
overall integrated leak rate, as specified
in the 10 CFR Part 50, Appendix J
definitions, includes the contribution
from MSIV leakage. By letter dated
October 6, 2004, the licensee has
requested an exemption from Option B,
Section III.A requirements to permit
exclusion of MSIV leakage from the
overall integrated leak rate test
measurement.
The above-cited requirement of
Appendix J requires that MSIV leakage
measurements be grouped with the
leakage measurements of other
containment penetrations when
containment leakage tests are
performed. These requirements are
inconsistent with the design of the
Brunswick facilities and the analytical
models used to calculate the
radiological consequences of designbasis accidents. At Brunswick and
similar facilities, the leakage from
primary containment penetrations
under accident conditions is collected
and treated by the secondary
containment system or would bypass
the secondary containment. However,
the leakage from MSIVs is collected and
treated via an Alternative Leakage
Treatment (ALT) path having different
mitigation characteristics. In performing
accident analyses, it is appropriate to
group various leakage effluents
according to the treatment they receive
before being released to the
environment, i.e., bypass leakage is
grouped, leakage into secondary
containment is grouped, and ALT
leakage is grouped, with specific limits
for each group defined in the TS. The
proposed exemption would permit ALT
path leakage to be independently
grouped with its unique leakage limits.
Environmental Impacts of the Proposed
Action
The proposed action will not
significantly increase the probability or
consequences of accidents. The NRC
staff has completed its evaluation of the
E:\FR\FM\07MRN1.SGM
07MRN1
Federal Register / Vol. 70, No. 43 / Monday, March 7, 2005 / Notices
proposed action and finds that the
proposed exemption involves no
increase in the total amount of
radioactive effluent that may be released
off site in the event of a design-basis
accident. Therefore, the calculated
doses remain within the acceptance
criteria of 10 CFR Part 100 and Standard
Review Plan Section 15, and there is no
significant increase in occupational or
public radiation exposure. The NRC
staff thus concludes that granting the
proposed exemption would result in no
significant radiological environmental
impact.
The proposed action does not affect
non-radiological plant effluents or
historical sites and has no other
environmental impact. Therefore, there
are no significant non-radiological
impacts associated with the proposed
exemption.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action.
Alternative 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 exemption
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
This action does not involve the use
of any resources not previously
considered in the Final Environmental
Statement dated January 1974 for the
Brunswick Steam Electric Plant, Unit
Nos. 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy,
on March 1, 2005, the NRC staff
consulted with the North Carolina State
official, Ms. Wendy Tingle of the North
Carolina Department of Environmental
and Natural Resources, Division of
Radiation Protection, regarding the
environmental impact of the proposed
action. Ms. Tingle 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 October 6, 2004. Documents may
VerDate jul<14>2003
18:15 Mar 04, 2005
Jkt 205001
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 O1F21, 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 by e-mail
to pdr@nrc.gov.
Dated at Rockville, Maryland, this 28th day
of February, 2005.
For the Nuclear Regulatory Commission.
Brenda L. Mozafari,
Senior Project Manager, Section 2, Project
Directorate II, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. 05–4312 Filed 3–4–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Material Control and Accounting at
Reactors and Wet Spent Fuel Storage
Facilities
Nuclear Regulatory
Commission.
AGENCY:
ACTION:
Notice of issuance.
SUMMARY: The Nuclear Regulatory
Commission (NRC) has issued Bulletin
(BL) 2005–01 to all holders of operating
licenses for nuclear power reactors,
decommissioning nuclear power reactor
sites storing spent fuel in a pool, and
wet spent fuel storage sites. This
bulletin contains sensitive information
relating to material control and
accounting (MC&A) programs and is,
therefore, being withheld from public
disclosure in accordance with 10 CFR
2.390. The bulletin is being provided to
only those licensees needing to respond
to it.
The bulletin was issued on
February 11, 2005.
DATES:
ADDRESSES:
Not applicable.
FOR FURTHER INFORMATION CONTACT:
Martha Williams, at 301–415–7878,
Glenn Tuttle, at 301–415–7644, or Dori
Votolato, at 301–415–7633.
Dated at Rockville, Maryland, this 28th day
of February 2005.
PO 00000
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11035
For the Nuclear Regulatory Commission.
Patrick L Hiland,
Chief, Reactor Operations Branch, Division
of Inspection Program Management, Office
of Nuclear Reactor Regulation.
[FR Doc. 05–4313 Filed 3–4–05; 8:45 am]
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RAILROAD RETIREMENT BOARD
Agency Forms Submitted for OMB
Review
SUMMARY: In accordance with the
Paperwork Reduction Act of 1995 (44
U.S.C. Chapter 35), the Railroad
Retirement Board (RRB) has submitted
the following proposal(s) for the
collection of information to the Office of
Management and Budget for review and
approval.
Summary of Proposal(s):
(1) Collection title: Representative
Payee Parental Custody Monitoring.
(2) Form(s) submitted: G–99d.
(3) OMB Number: 3220–0176.
(4) Expiration date of current OMB
clearance: May 31, 2005.
(5) Type of request: Extension of a
currently approved collection.
(6) Respondents: Individuals or
households.
(7) Estimated annual number of
respondents: 1,230.
(8) Total annual responses: 1,2300.
(9) Total annual reporting hours: 103.
(10) Collection description: Under
section 12(a) of the Railroad Retirement
Act, the RRB is authorized to select,
make payments to, and conduct
transactions with an annuitant’s relative
or some other person willing to act on
behalf of the annuitant as a
representative payee. The collection
obtains information needed to verify the
parent-for-child payee still retains
custody of the child.
Additional Information or Comments:
Copies of the forms and supporting
documents can be obtained from
Charles Mierzwa, the agency clearance
officer at (312) 751–3363 or
Charles.Mierzwa@rrb.gov.
Comments regarding the information
collection should be addressed to
Ronald J. Hodapp, Railroad Retirement
Board, 844 North Rush Street, Chicago,
Illinois, 60611–2092 or
Ronald.Hodapp@rrb.gov and to the
OMB Desk Officer for the RRB, at the
Office of Management and Budget,
Room 10230, New Executive Office
Building, Washington, DC 20503.
Charles Mierzwa,
Clearance Officer.
[FR Doc. 05–4305 Filed 3–4–05; 8:45 am]
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]]>Agencies
[Federal Register Volume 70, Number 43 (Monday, March 7, 2005)]
[Notices]
[Pages 11034-11035]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-4312]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-325 and 50-324]
Carolina Power & Light Company, Brunswick Steam Electric Plant,
Unit Nos. 1 and 2; Environmental Assessment and Finding of No
Significant Impact
Introduction
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption from 10 CFR Part 50, Appendix J for Facility
Operating Licenses Nos. DPR-71 and DPR-62 issued to the Carolina Power
& Light Company (the licensee, also doing business as Progress Energy
Carolinas, Inc.) for operation of the Brunswick Steam Electric Plant,
Unit Nos. 1 and 2 located in Brunswick County, North Carolina.
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt the licensee from requirements to
include main steam isolation valve (MSIV) leakage in the overall
integrated leakage rate test measurement required by Section III.A of
Appendix J, Option B.
The proposed action is in accordance with the licensee's
application dated October 6, 2004, for exemption from certain
requirements of Title 10 of the Code of Federal Regulations (10 CFR),
Part 50, Appendix J.
The Need for the Proposed Action
Section 50.54(o) of 10 CFR Part 50 requires that primary reactor
containments for water-cooled power reactors be subject to the
requirements of Appendix J to 10 CFR Part 50. Appendix J specifies the
leakage test requirements, schedules, and acceptance criteria for tests
of the leaktight integrity of the primary reactor containment and
systems and components that penetrate the containment. Option B,
Section III.A requires that the overall integrated leak rate must not
exceed the allowable leakage (La) with margin, as specified in the
Technical Specifications (TS). The overall integrated leak rate, as
specified in the 10 CFR Part 50, Appendix J definitions, includes the
contribution from MSIV leakage. By letter dated October 6, 2004, the
licensee has requested an exemption from Option B, Section III.A
requirements to permit exclusion of MSIV leakage from the overall
integrated leak rate test measurement.
The above-cited requirement of Appendix J requires that MSIV
leakage measurements be grouped with the leakage measurements of other
containment penetrations when containment leakage tests are performed.
These requirements are inconsistent with the design of the Brunswick
facilities and the analytical models used to calculate the radiological
consequences of design-basis accidents. At Brunswick and similar
facilities, the leakage from primary containment penetrations under
accident conditions is collected and treated by the secondary
containment system or would bypass the secondary containment. However,
the leakage from MSIVs is collected and treated via an Alternative
Leakage Treatment (ALT) path having different mitigation
characteristics. In performing accident analyses, it is appropriate to
group various leakage effluents according to the treatment they receive
before being released to the environment, i.e., bypass leakage is
grouped, leakage into secondary containment is grouped, and ALT leakage
is grouped, with specific limits for each group defined in the TS. The
proposed exemption would permit ALT path leakage to be independently
grouped with its unique leakage limits.
Environmental Impacts of the Proposed Action
The proposed action will not significantly increase the probability
or consequences of accidents. The NRC staff has completed its
evaluation of the
[[Page 11035]]
proposed action and finds that the proposed exemption involves no
increase in the total amount of radioactive effluent that may be
released off site in the event of a design-basis accident. Therefore,
the calculated doses remain within the acceptance criteria of 10 CFR
Part 100 and Standard Review Plan Section 15, and there is no
significant increase in occupational or public radiation exposure. The
NRC staff thus concludes that granting the proposed exemption would
result in no significant radiological environmental impact.
The proposed action does not affect non-radiological plant
effluents or historical sites and has no other environmental impact.
Therefore, there are no significant non-radiological impacts associated
with the proposed exemption.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
Alternative 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 exemption 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
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement dated
January 1974 for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy, on March 1, 2005, the NRC
staff consulted with the North Carolina State official, Ms. Wendy
Tingle of the North Carolina Department of Environmental and Natural
Resources, Division of Radiation Protection, regarding the
environmental impact of the proposed action. Ms. Tingle 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 October 6, 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, Public File Area O1F21, 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 by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 28th day of February, 2005.
For the Nuclear Regulatory Commission.
Brenda L. Mozafari,
Senior Project Manager, Section 2, Project Directorate II, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 05-4312 Filed 3-4-05; 8:45 am]
BILLING CODE 7590-01-P
