Portland General Electric; Trojan Independent Spent Fuel Storage Installation; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a License Amendment, 13435-13437 [E6-3714]
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Federal Register / Vol. 71, No. 50 / Wednesday, March 15, 2006 / Notices
financial disclosure statements to avoid
conflict-of-interest issues. The security
background check will involve the
completion and submission of
paperwork to NRC and will take
approximately four weeks to complete.
Dated at Rockville, Maryland this 9th day
of March, 2006.
For the Nuclear Regulatory Commission.
Andrew L. Bates,
Advisory Committee Management Officer.
[FR Doc. E6–3716 Filed 3–14–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 040–08838]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment for the Department of the
Army’s Facility at Jefferson Proving
Ground
Nuclear Regulatory
Commission.
ACTION: Notice of Availability.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
sroberts on PROD1PC70 with NOTICES
Thomas McLaughlin, Project Manager,
Decommissioning Directorate, Division
of Waste Management and
Environmental Protection, Office of
Nuclear Material Safety and Safeguards,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001;
Telephone: (301) 415–5869; fax number:
(301) 415–5398; e-mail: tgm@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The Nuclear Regulatory Commission
(NRC) is considering issuance of a
license amendment to the Department of
the Army (Army or licensee) for License
No. SUB–1435. The amendment would
authorize an alternate decommissioning
schedule pursuant to 10 Code of Federal
Regulations (CFR) part 40.42(g)(2), for
the Army to conduct site
characterization and prepare and submit
a decommissioning plan for its facility
at Jefferson Proving Ground, Madison,
Indiana. NRC has prepared an
Environmental Assessment (EA) in
support of this action in accordance
with the requirements of 10 CFR part
51. Based on the EA, the NRC has
concluded that a Finding of No
Significant Impact (FONSI) is
appropriate.
II. EA Summary
The purpose of this proposed action
is to amend Radioactive Materials
License SUB–1435 to allow the Army to
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17:27 Mar 14, 2006
Jkt 208001
decommission its Jefferson Proving
Ground facility using an alternate
schedule for submittal of a
decommissioning plan pursuant to 10
CFR part 40.42(g)(2). The Army is
requesting a 5-year period to
characterize the site and submit a
decommissioning plan. The Army’s
request is contained in a letter to NRC
dated May 25, 2005.
The NRC staff has determined that all
steps in the proposed site
characterization could be accomplished
in compliance with the NRC public and
occupational dose limits and effluent
release limits. In addition, the staff has
concluded that approval of the alternate
decommissioning schedule would not
result in a significant adverse
radiological or non-radiological impact
on the environment.
If the NRC approves the license
amendment, the authorization will be
documented in an amendment to NRC
License No. SUB–1435. However, before
approving the proposed amendment, the
NRC will need to make the findings
required by the Atomic Energy Act of
1954, as amended, and NRC’s
regulations. These findings will be
documented in a Safety Evaluation
Report in addition to the EA.
III. Finding of No Significant Impact
The staff has prepared the EA
(summarized above) in support of the
Army’s proposed alternate schedule for
submittal of a decommissioning plan.
The NRC staff has concluded that there
will be no significant adverse
environmental impacts associated with
approving the Army’s license
amendment request. On the basis of the
EA, the NRC has concluded that the
environmental impacts from the action
are expected to be insignificant and has
determined not to prepare an
environmental impact statement for the
action.
IV. Further Information
Documents related to this action,
including the application for
amendment and supporting
documentation, are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agency-wide
Document Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The ADAMS accession
number for the documents related to
this notice are: The Army’s letter to NRC
dated May 25, 2005, ML051520319; the
EA prepared for this action,
ML053130257; Federal Register Notice
for Amendment No. 13, ML053220289.
PO 00000
Frm 00104
Fmt 4703
Sfmt 4703
13435
If you do not have access to ADAMS or
if there are problems in accessing the
documents located in ADAMS, contact
the NRC Public Document Room (PDR)
Reference staff at 1–800–397–4209, 301–
415–4737, or by e-mail to pdr@nrc.gov.
Any questions should be referred to
Thomas McLaughlin, Division of Waste
Management and Environmental
Protection, U.S. Nuclear Regulatory
Commission, Washington DC 20555,
Mailstop T–7E18, telephone (301) 415–
5869, fax (301) 415–5397.
Dated at Rockville, Maryland, this seventh
day of March, 2006.
For the Nuclear Regulatory Commission.
Claudia M. Craig,
Acting Deputy Director, Decommissioning
Directorate, Division of Waste Management
and Environmental Protection, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. E6–3715 Filed 3–14–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–17]
Portland General Electric; Trojan
Independent Spent Fuel Storage
Installation; Issuance of Environmental
Assessment and Finding of No
Significant Impact Regarding a License
Amendment
Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact.
AGENCY:
Jill
S. Caverly, Project Manager, Spent Fuel
Project Office, Office of Nuclear
Material Safety and Safeguards, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555. Telephone:
(301) 415–6699; Fax number: (301) 415–
8555; E-mail: jsc1@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Introduction
The U.S. Nuclear Regulatory
Commission (NRC, or the staff) is
considering issuance of a license
amendment to the Portland General
Electric Company (PGE, or the licensee)
for Special Nuclear Materials License
SNM–2509. An Environmental
Assessment was issued at the time of
the application for the license and a
determination of a Finding of No
Significant Impact was finalized on
November 11, 1996. The current
amendment request was submitted to
the NRC under letter dated May 23,
2005, [ADAMS Accession Number
ML051460408]. The request is in
E:\FR\FM\15MRN1.SGM
15MRN1
13436
Federal Register / Vol. 71, No. 50 / Wednesday, March 15, 2006 / Notices
accordance with 10 Code of Federal
Regulations (CFR) 72.48(c)(2) and 10
CFR 72.56 for a license amendment that
would approve a change that would
result in a departure from a method of
evaluation described in the Trojan
Independent Spent Fuel Storage
Installation (ISFSI) Safety Analysis
Report (SAR). An ISFSI is defined in 10
CFR part 72 as ‘‘a complex designed and
constructed for the interim storage of
spent nuclear fuel, solid reactor related
waste * * * and other radioactive
materials associated with spent
fuel. * * *’’ The result of the
amendment would be revised
methodology used to determine the
controlled area boundary for the ISFSI,
which would reduce the controlled area
(controlled area as defined in 10 CFR
part 20) from 300 meters from the edge
of the concrete storage pad to 200
meters from the edge of the pad.
Environmental Assessment (EA)
sroberts on PROD1PC70 with NOTICES
I. Identification of Proposed Action
The Trojan ISFSI is located at PGE’s
former Trojan Nuclear Plant near
Rainier, Oregon. The proposed action
before the NRC is the approval of
methodology for determining the
controlled area at the ISFSI that will
result in moving the boundary of the
controlled area. PGE has requested a
license amendment in accordance with
10 CFR 72.48(c)(2) and 10 CFR 72.56 to
revise the method of evaluation used in
the SAR for determining the controlled
area of the Trojan ISFSI. The current
Trojan ISFSI Controlled Area boundary
was established at 300 meters based on
the results of the Trojan ISFSI shielding
and confinement analyses and the
requirements of 10 CFR 72.104 and
72.106. The current shielding analysis
was performed prior to loading the
ISFSI storage casks to conservatively
predict dose rates. For the proposed
license amendment, PGE revised the
shielding calculation to include actual
direct radiation measurements. The
revised calculations show that the
requirements of 10 CFR part 72 are met
if the controlled area is reduced from
300 meters from the edge of the pad to
200 meters to the edge of the pad. The
proposed action will not require any
physical changes to fences or
construction at the site but will relocate
dosimeters to 200 meters from the edge
of the pad.
II. Need for the Proposed Action
PGE is seeking this reduction of the
Trojan ISFSI Controlled Area primarily
to facilitate the efficient long-term
management and security of the spent
nuclear fuel and fuel-related materials
VerDate Aug<31>2005
17:27 Mar 14, 2006
Jkt 208001
stored in the ISFSI. This change would
eliminate the Trojan ISFSI’s program
and procedural requirements for access
controls on site areas for which such
controls are not necessary or warranted
to ensure the protection of the health
and safety of the public and the
environment. PGE has completed
decommissioning of the adjoining 10
CFR part 50 site and seeks to
consolidate the remaining area of its
responsibility. The area between the
current and revised controlled area has
been analyzed for contamination under
the Trojan Nuclear Plant’s
decommissioning program. A final
radiologic survey will be required at the
time of ISFSI decommissioning.
III. Environmental Impacts of the
Proposed Action
The staff has determined that
although the proposed action will result
in a reduction in the current controlled
area boundary, the ISFSI will continue
to meet the requirements of 10 CFR part
72. The proposed action does not
involve a significant increase in the
probability or consequences of an event
or accident previously evaluated nor
does it create a possibility of a new or
different kind of event. The staff
concludes that there is reasonable
assurance that the proposed changes in
the methodology will have no impact on
off-site radiation doses. Additionally,
the staff has determined that there
would be no impacts to the environment
from the proposed action.
IV. Alternative to the Proposed Action
As an alternative to the proposed
action, the staff considered denial of the
amendment request (i.e., the ‘‘noaction’’ alternative). Thus, the no action
alternative would leave the current
controlled area boundary in place at 300
meters from the edge of the concrete
storage pad. No environmental impacts
would result from the no action
alternative.
V. Agencies and Persons Consulted
The NRC staff prepared this
environmental assessment (EA). The
U.S. Fish and Wildlife Service’s
Threatened and Endangered Species
System was consulted and reviewed as
well the species analysis in the EA
conducted for the original ISFSI license
(November 1996). Based on the very
limited activity of moving dosimeters
and the staff’s overall analysis,
involvement of the human environment
is minimal for this proposed action and
essentially the same as the current
environmental conditions. Hence, this
action does not warrant consultation for
further input and analysis under section
PO 00000
Frm 00105
Fmt 4703
Sfmt 4703
7 of the Endangered Species Act or
section 106 of the National Historic
Preservation Act.
VI. Conclusions
The staff analysis of the PGE proposed
amendment concludes that issuing the
amendment to allow for a revised
methodology to calculate the boundary
of the controlled area in the SAR will
not result in significant environmental
consequences. Hence, the staff
recommends a Finding of No Significant
Impact.
VII. Sources
NRC, Environmental Assessment
dated November 1996.
PGE, application dated May 23, 2005.
PGE, Safety Analysis Report, Rev 6.,
dated July 21, 2005.
U.S. Fish and Wildlife Service,
Threatened and Endangered Species
System (https://www.fws.gov).
Finding of No Significant Impact
The environmental impacts of the
proposed action have been reviewed in
accordance with the requirements set
forth in 10 CFR part 51. Based upon the
foregoing EA, the NRC finds that the
proposed action of approving the
amendment to the license will not
significantly impact the quality of the
human environment. Accordingly, the
NRC has determined that an
environmental impact statement for the
proposed amendment is not warranted.
Further Information
In accordance with 10 CFR 2.390 of
NRC’s ‘‘Rules of Practice,’’ final NRC
records and documents regarding this
proposed action, including the
amendment request dated May 23, 2005,
are publicly available in the records
component of NRC’s Agencywide
Documents Access and Management
System (ADAMS). These documents
may be inspected at NRC’s Public
Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html.
These documents may also be viewed
electronically on the public computers
located at the NRC’s Public Document
Room (PDR), O1F21, One White Flint
North, 11555 Rockville Pike, Rockville,
MD 20852. The PDR reproduction
contractor will copy documents for a
fee. 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 email to pdr@nrc.gov.
Dated at Rockville, Maryland, this 6th day
of March 2006.
E:\FR\FM\15MRN1.SGM
15MRN1
Federal Register / Vol. 71, No. 50 / Wednesday, March 15, 2006 / Notices
For the Nuclear Regulatory Commission.
Jill Caverly,
Project Manager, Licensing Section, Spent
Fuel Project Office, Office of Nuclear Material
Safety and Safeguards.
[FR Doc. E6–3714 Filed 3–14–06; 8:45 am]
BILLING CODE 7590–01–P
PENSION BENEFIT GUARANTY
CORPORATION
Required Interest Rate Assumption for
Determining Variable-Rate Premium for
Single-Employer Plans; Interest
Assumptions for Multiemployer Plan
Valuations Following Mass Withdrawal
Pension Benefit Guaranty
Corporation.
ACTION: Notice of interest rates and
assumptions.
AGENCY:
sroberts on PROD1PC70 with NOTICES
SUMMARY: This notice informs the public
of the interest rates and assumptions to
be used under certain Pension Benefit
Guaranty Corporation regulations. These
rates and assumptions are published
elsewhere (or can be derived from rates
published elsewhere), but are collected
and published in this notice for the
convenience of the public. Interest rates
are also published on the PBGC’s Web
site (https://www.pbgc.gov).
DATES: The required interest rate for
determining the variable-rate premium
under part 4006 applies to premium
payment years beginning in March
2006. The interest assumptions for
performing multiemployer plan
valuations following mass withdrawal
under part 4281 apply to valuation dates
occurring in April 2006.
FOR FURTHER INFORMATION CONTACT:
Catherine B. Klion, Attorney, Legislative
and Regulatory Department, Pension
Benefit Guaranty Corporation, 1200 K
Street, NW., Washington, DC 20005,
202–326–4024. (TTY/TDD users may
call the Federal relay service toll-free at
1–800–877–8339 and ask to be
connected to 202–326–4024.)
SUPPLEMENTARY INFORMATION:
Variable-Rate Premiums
Section 4006(a)(3)(E)(iii)(II) of the
Employee Retirement Income Security
Act of 1974 (ERISA) and § 4006.4(b)(1)
of the PBGC’s regulation on Premium
Rates (29 CFR part 4006) prescribe use
of an assumed interest rate (the
‘‘required interest rate’’) in determining
a single-employer plan’s variable-rate
premium. The required interest rate is
the ‘‘applicable percentage’’ (currently
85 percent) of the annual yield on 30year Treasury securities for the month
preceding the beginning of the plan year
for which premiums are being paid (the
VerDate Aug<31>2005
17:27 Mar 14, 2006
Jkt 208001
‘‘premium payment year’’). (After a fiveyear hiatus, the Treasury Department
issued 30-year securities during
February 2006. To take yields on the
new securities into account, the Internal
Revenue Service has determined the
annual yield on 30-year Treasury
securities for February 2006 to be the
average of the yield on the 30-year
Treasury bond maturing in February
2031 determined each business day in
February 2006 through February 8,
2006, and the yield on the 30-year
Treasury bond maturing in February
2036 determined each business day for
the balance of February 2006. The
required interest rate to be used in
determining variable-rate premiums for
premium payment years beginning in
March 2006 is 3.89 percent (i.e., 85
percent of the 4.58 percent Treasury
securities rate for February 2006).
The Pension Funding Equity Act of
2004 (‘‘PFEA’’)—under which the
required interest rate is 85 percent of the
annual rate of interest determined by
the Secretary of the Treasury on
amounts invested conservatively in
long-term investment grade corporate
bonds for the month preceding the
beginning of the plan year for which
premiums are being paid—applies only
for premium payment years beginning
in 2004 or 2005. Congress is considering
legislation that would extend the PFEA
rate for one more year. If legislation that
changes the rules for determining the
required interest rate for plan years
beginning in March 2006 is adopted, the
PBGC will promptly publish a Federal
Register notice with the new rate.
The following table lists the required
interest rates to be used in determining
variable-rate premiums for premium
payment years beginning between April
2005 and March 2006.
For premium payment years beginning in:
April 2005 .....................................
May 2005 ......................................
June 2005 .....................................
July 2005 ......................................
August 2005 .................................
September 2005 ...........................
October 2005 ................................
November 2005 ............................
December 2005 ............................
January 2006 ................................
February 2006 ..............................
March 2006 ...................................
The
required
interest
rate is:
4.78
4.72
4.60
4.47
4.56
4.61
4.62
4.83
4.91
3.95
3.90
3.89
Multiemployer Plan Valuations
Following Mass Withdrawal
The PBGC’s regulation on Duties of
Plan Sponsor Following Mass
Withdrawal (29 CFR part 4281)
PO 00000
Frm 00106
Fmt 4703
Sfmt 4703
13437
prescribes the use of interest
assumptions under the PBGC’s
regulation on Allocation of Assets in
Single-Employer Plans (29 CFR part
4044). The interest assumptions
applicable to valuation dates in April
2006 under part 4044 are contained in
an amendment to part 4044 published
elsewhere in today’s Federal Register
Tables showing the assumptions
applicable to prior periods are codified
in appendix B to 29 CFR part 4044.
Issued in Washington, DC, on this 8th day
of March 2006.
Vincent K. Snowbarger,
Deputy Executive Director, Pension Benefit
Guaranty Corporation.
[FR Doc. E6–3699 Filed 3–14–06; 8:45 am]
BILLING CODE 7709–01–P
SECURITIES AND EXCHANGE
COMMISSION
[File No. 1–31227]
Issuer Delisting; Notice of Application
of Cogent Communications Group, Inc.
To Withdraw Its Common Stock, $.001
Par Value, From Listing and
Registration on the American Stock
Exchange LLC
March 9, 2006.
On March 3, 2006, Cogent
Communications Group, Inc., a
Delaware corporation (‘‘Issuer’’), filed
an application with the Securities and
Exchange Commission (‘‘Commission’’),
pursuant to Section 12(d) of the
Securities Exchange Act of 1934
(‘‘Act’’) 1 and Rule 12d2–2(d)
thereunder,2 to withdraw its common
stock, $.001 par value (‘‘Security’’), from
listing and registration on the American
Stock Exchange LLC (‘‘Amex’’).
The Board of Directors (‘‘Board’’) of
the Issuer approved resolutions on July
11, 2005, and confirmed such
authorization on February 7, 2006 to
withdraw the Security from listing on
Amex and register and list the Security
on the Nasdaq National Market
(‘‘Nasdaq’’). The Board believes that
Nasdaq will provide greater exposure of
the Security to investors, especially as
more members of the Issuer’s peer group
of communications companies have a
Nasdaq listing rather than an exchange
listing. The Issuer stated that on
February 28, 2006, Nasdaq approved the
Issuer’s application to list the Security
on Nasdaq. The Issuer expects the
Security to trade on Nasdaq on or about
March 6, 2006.
1 15
2 17
U.S.C. 78l(d).
CFR 240.12d2–2(d).
E:\FR\FM\15MRN1.SGM
15MRN1
]]>Agencies
[Federal Register Volume 71, Number 50 (Wednesday, March 15, 2006)]
[Notices]
[Pages 13435-13437]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-3714]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 72-17]
Portland General Electric; Trojan Independent Spent Fuel Storage
Installation; Issuance of Environmental Assessment and Finding of No
Significant Impact Regarding a License Amendment
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Jill S. Caverly, Project Manager,
Spent Fuel Project Office, Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
Telephone: (301) 415-6699; Fax number: (301) 415-8555; E-mail:
jsc1@nrc.gov.
Introduction
The U.S. Nuclear Regulatory Commission (NRC, or the staff) is
considering issuance of a license amendment to the Portland General
Electric Company (PGE, or the licensee) for Special Nuclear Materials
License SNM-2509. An Environmental Assessment was issued at the time of
the application for the license and a determination of a Finding of No
Significant Impact was finalized on November 11, 1996. The current
amendment request was submitted to the NRC under letter dated May 23,
2005, [ADAMS Accession Number ML051460408]. The request is in
[[Page 13436]]
accordance with 10 Code of Federal Regulations (CFR) 72.48(c)(2) and 10
CFR 72.56 for a license amendment that would approve a change that
would result in a departure from a method of evaluation described in
the Trojan Independent Spent Fuel Storage Installation (ISFSI) Safety
Analysis Report (SAR). An ISFSI is defined in 10 CFR part 72 as ``a
complex designed and constructed for the interim storage of spent
nuclear fuel, solid reactor related waste * * * and other radioactive
materials associated with spent fuel. * * *'' The result of the
amendment would be revised methodology used to determine the controlled
area boundary for the ISFSI, which would reduce the controlled area
(controlled area as defined in 10 CFR part 20) from 300 meters from the
edge of the concrete storage pad to 200 meters from the edge of the
pad.
Environmental Assessment (EA)
I. Identification of Proposed Action
The Trojan ISFSI is located at PGE's former Trojan Nuclear Plant
near Rainier, Oregon. The proposed action before the NRC is the
approval of methodology for determining the controlled area at the
ISFSI that will result in moving the boundary of the controlled area.
PGE has requested a license amendment in accordance with 10 CFR
72.48(c)(2) and 10 CFR 72.56 to revise the method of evaluation used in
the SAR for determining the controlled area of the Trojan ISFSI. The
current Trojan ISFSI Controlled Area boundary was established at 300
meters based on the results of the Trojan ISFSI shielding and
confinement analyses and the requirements of 10 CFR 72.104 and 72.106.
The current shielding analysis was performed prior to loading the ISFSI
storage casks to conservatively predict dose rates. For the proposed
license amendment, PGE revised the shielding calculation to include
actual direct radiation measurements. The revised calculations show
that the requirements of 10 CFR part 72 are met if the controlled area
is reduced from 300 meters from the edge of the pad to 200 meters to
the edge of the pad. The proposed action will not require any physical
changes to fences or construction at the site but will relocate
dosimeters to 200 meters from the edge of the pad.
II. Need for the Proposed Action
PGE is seeking this reduction of the Trojan ISFSI Controlled Area
primarily to facilitate the efficient long-term management and security
of the spent nuclear fuel and fuel-related materials stored in the
ISFSI. This change would eliminate the Trojan ISFSI's program and
procedural requirements for access controls on site areas for which
such controls are not necessary or warranted to ensure the protection
of the health and safety of the public and the environment. PGE has
completed decommissioning of the adjoining 10 CFR part 50 site and
seeks to consolidate the remaining area of its responsibility. The area
between the current and revised controlled area has been analyzed for
contamination under the Trojan Nuclear Plant's decommissioning program.
A final radiologic survey will be required at the time of ISFSI
decommissioning.
III. Environmental Impacts of the Proposed Action
The staff has determined that although the proposed action will
result in a reduction in the current controlled area boundary, the
ISFSI will continue to meet the requirements of 10 CFR part 72. The
proposed action does not involve a significant increase in the
probability or consequences of an event or accident previously
evaluated nor does it create a possibility of a new or different kind
of event. The staff concludes that there is reasonable assurance that
the proposed changes in the methodology will have no impact on off-site
radiation doses. Additionally, the staff has determined that there
would be no impacts to the environment from the proposed action.
IV. Alternative to the Proposed Action
As an alternative to the proposed action, the staff considered
denial of the amendment request (i.e., the ``no-action'' alternative).
Thus, the no action alternative would leave the current controlled area
boundary in place at 300 meters from the edge of the concrete storage
pad. No environmental impacts would result from the no action
alternative.
V. Agencies and Persons Consulted
The NRC staff prepared this environmental assessment (EA). The U.S.
Fish and Wildlife Service's Threatened and Endangered Species System
was consulted and reviewed as well the species analysis in the EA
conducted for the original ISFSI license (November 1996). Based on the
very limited activity of moving dosimeters and the staff's overall
analysis, involvement of the human environment is minimal for this
proposed action and essentially the same as the current environmental
conditions. Hence, this action does not warrant consultation for
further input and analysis under section 7 of the Endangered Species
Act or section 106 of the National Historic Preservation Act.
VI. Conclusions
The staff analysis of the PGE proposed amendment concludes that
issuing the amendment to allow for a revised methodology to calculate
the boundary of the controlled area in the SAR will not result in
significant environmental consequences. Hence, the staff recommends a
Finding of No Significant Impact.
VII. Sources
NRC, Environmental Assessment dated November 1996.
PGE, application dated May 23, 2005.
PGE, Safety Analysis Report, Rev 6., dated July 21, 2005.
U.S. Fish and Wildlife Service, Threatened and Endangered Species
System (https://www.fws.gov).
Finding of No Significant Impact
The environmental impacts of the proposed action have been reviewed
in accordance with the requirements set forth in 10 CFR part 51. Based
upon the foregoing EA, the NRC finds that the proposed action of
approving the amendment to the license will not significantly impact
the quality of the human environment. Accordingly, the NRC has
determined that an environmental impact statement for the proposed
amendment is not warranted.
Further Information
In accordance with 10 CFR 2.390 of NRC's ``Rules of Practice,''
final NRC records and documents regarding this proposed action,
including the amendment request dated May 23, 2005, are publicly
available in the records component of NRC's Agencywide Documents Access
and Management System (ADAMS). These documents may be inspected at
NRC's Public Electronic Reading Room at https://www.nrc.gov/reading-rm/
adams.html. These documents may also be viewed electronically on the
public computers located at the NRC's Public Document Room (PDR),
O1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD
20852. The PDR reproduction contractor will copy documents for a fee.
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 6th day of March 2006.
[[Page 13437]]
For the Nuclear Regulatory Commission.
Jill Caverly,
Project Manager, Licensing Section, Spent Fuel Project Office, Office
of Nuclear Material Safety and Safeguards.
[FR Doc. E6-3714 Filed 3-14-06; 8:45 am]
BILLING CODE 7590-01-P
